ACCELERATED DlBUTTON DEMONSTR+10N SYSTEM

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 8906050261 DOC. DATE: 89/05/19 NOTARIZED: NOFACIL:50-410 Nine Mile Point Nuclear Station, Unit 2, Niagara Moha

AUTH.NAME AUTHOR AFFILIATIONTERRY,C.D. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFXLIATIONDocument Control Branch (Document Control Desk)

DOCKET I05000410

SUBJECT: Provides addi info re NMP-2 first 10 yr inservice inspprogram.

DISTRIBUTXON CODE: A047D COPIES RECEIVED:LTR ENCL SIZE:TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME Code

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Y NIAGARU hMHAWK

NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, N,Y. 13212/TELEPHONE (315) 474-1511

May 19, 1989NMP2L 1199

U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555

Re: Nine Mile Point Unit 2Docket No. 50-410

NPF-69TAC No. 66071

Gentlemen:

This letter provides additional information regarding the Nine Mile Point Unit2 First 10 Year Inservice Inspection Program. This information was requestedby the Commission's staff in a letter dated November 25, 1987. NiagaraMohawk's letter of February 12, 1988 committed to provide this informationafter completion of the Midcycle

Outage't

is Niagara Mohawk's opinion that a relief request is required when lessthan 901. of the code required volume or surface area is accessible forexamination. This position is consistent with ASME Code Case N-460. He haveapplied this philosophy to the enclosed relief requests.

He have reviewed and re-evaluated Requests for Relief Numbers RR-IWB-6 andRR-IWC-4. Request for Relief RR-IHB-6 has been revised to delete thereference to the sweepolets ~ A valid examination was performed from the pipeside. Request for Relief RR-IHC-4 was revised to incorporate the results ofsupplemental surface examinations of integral attachments.

We have also revised relief request RR-IWB-4 and RR-IHC-2 to includeadditional inaccessible welds. RR-IHB-12 was revised to reflect thereplacement of the Main Steam Isolation Valves.

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Niagara Mohawk has restructured our Inservice Inspection organization toprovide better supervision and control of inspection activities. One part ofour long range program to improve ISI will be a re-evaluation of reliefrequests. Each relief request will be re-evaluated over the 10 yearinspection interval to take advantage of improvements in examinationtechniques.

Very truly yours,

NIAGARA MOHAWK POWER CORPORATION

KBT/mlf6636GAttachments

C. D. TerryVice President

Nuclear Engineering & Licensing

xc: Regional Administrator, Region IMr. R. A. Capra, DirectorMs. M. L. Slosson, Project ManagerMr. W. A. Cook, Resident InspectorRecords Management

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Section IAppendix F

Page 20Rev. 1

RELIEF REQUEST NO. RR-IHB-6

Component(s): Stainless steel piping welds on the Reactor Coolant,Residual Heat Removal, and Reactor Hater Cleanup systems.

Welds: 2RCS-64-00-SN0032RCS-64-00-FHA012RCS-64-00-FHA052RCS-64-00-FNB01

2RCS-64-00-FNB082RHS-66-55-FH0012NCS-09-05-SN0202HCS-09-05-SN025

Class:

ExaminationRequirement(s):

Basis for Relief:

Volumetric and surface examinations are required for thesewelds per Table INB-2500-1, Category B-J, Items B9.11.

The accessibility for volumetric examination of thesewelds is limited due to piping system design and fittingconfiguration. These welds can only be examined from oneside using the UT techniques recommended by EPRI. Thespecific fitting configuration and side from which theexamination can be performed are contained in Table l.Structural integrity of these welds was verified duringerection by volumetric and surface examinations under ASMESection III.NMPC is of the opinion that one sided scans and thesurface examinations that will be employed provide areasonable degree of confidence in the integrity of thesewelds.

AlternateExamination(s): Niagara Mohawk will use the best UT techniques available

during scheduled inservice examination. This reliefrequest will be revised if additional coverage is obtained.

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Section IAppendix F

Page 22Rev. 1

RELIEF REQUEST NO. RR-IWB-6 (Cont.)

TABLE 1

CAT

B-J

B-J

B-J

B-J

B-J

B-J

B-J B9.11 2WCS-09-05-SH020

HELD NO.

B9.11 2RCS-64-00-SW003

B9.11 2RCS-64-00-FHA01

B9.11 2RCS-64-00-FWA05

B9.11 2RCS-64-00-FWB01

B9.11 2RCS-64-00-FWB08

B9.11 2RHS-66-55-FH001

B9.11 2WCS-09-05-SW025

CONFIGURATION

Pipe to Flange

Pipe to Safe End Ext.

Elbow to Pump

Pipe to Safe End Ext.

Elbow to VLV

Pipe to Tee

Pipe to Flange

Pipe to Tee

EXAM FROM

Pipe side only

Pipe side only

Elbow side only

Pipe side only

Elbow side only

Pipe side only

Pipe side only

Pipe side only

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Section IAppendix F

Page 53Rev. 1

RELIEF REQUEST NO. RR-IHC-4

Component(s): Integral attachment welds on piping lugs to the ControlRod Drive System.

V(e Id s:

Class:

-2RDS-65-00-IAH018-12,-2RDS-65-00-IAH03A-12,-2RDS-65-00-IAN048-12,-2RDS-65-00-IAH06A-12,-2RDS-65-00-IAN078-12,-2RDS-65-00-IAN09A-16,-2RDS-65-00-IAH108-16,-2RDS-65-00-IAW12A-20,-2RDS-65-00-IAH138-20,-2RDS-65-00-IAW15A-20A

30, 31-2RDS-65-00-IAH168-20,-2RDS-65-00-IAN18A-20,-2RDS-65-00-IAW198-20,-2RDS-65-00-IAH22A-16,-2RDS-65-00-IAHSP2N-l,-2RDS-65-00-IAHSP2S-1,

13, 14, 15,13, 14, 15,13, 14, 15,13, 14, 15,13, 14, 15,17, 18, 19,17, 18, 19,21, 22, 23,21, 22, 23,

, 21A, 22A,

21, 22, 23,21, 22, 23,21, 22, 23,17, 18, 19,2, 3, 4, 5,2, 3, 4, 5,

16, 17, 18, 1916, 17, 18, 1916, 17, 18, 1916, 17, 18, 1916, 17, 18, 1920, 21, 22, 23, 24, 2520, 21, 22, 2324, 25, 26, 27, 30, 3124, 25, 26, 27, 32, 33

23A, 24A, 25A, 26A, 27A,

24, 25, 26, 27, 32, 3324, 25, 26, 27, 31, 3224, 25, 26, 27, 32, 3320, 21, 22, 23, 24, 256, 7, 86, 7, 8

ExaminationRequirement(s):

Basis for Relief:

AlternativeExaminations:

Surface examination is required for these integralattachment welds per Table IWC-2500-1 Category C-C, ItemC3.20.

Accessibility to perform surface examinations on thesewelds is limited due to interferences with the tube steelof their associated supports. Figure 1 contains a sketchwhich shows the typical configuration of these welds,including the area accessible for surface examination andthe limiting permanent interferences. The position of thetube steel relative to the lug is required for the supportto perform its design function. The integrity of thesewelds were verified by nondestructive examination duringerection under ASME Section III.In order to fully comply with the Section XI requirements,major redesign and modification would be required withouta compensating increase in the level of quality or safety.

Surface examinations will be performed to the maximumextent possible.

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Section IAppendix F

Page 17Rev. 1

Component(s):

RELIEF REQUEST NO. RR-INC-2

Stainless steel piping welds on the Residual HeatRemoval and Core Spray Systems.

Welds: 2CSH-25-05-FN0122CSH-25-05-FN0132CSH-25-05-FN0142CSH-25-05-FN0152CSL-26-01-FN0262CSL-26-01-FN0272CSL-26-01-FN0282CSL-26-01-FN0352RHS-66-13-FN0232RHS-66-13-FN0242RHS-66-13-FN025

2RHS-66-13-FN0292RHS-66-22-FN0212RHS-66-22-FN0222RHS-66-22-FW0232RHS-66-22-FW0292RHS-66-23-FW0182RHS-66-23-FN0192RHS-66-23-FN0202RHS-66-23-FN022

Class:

ExaminationRequirement:

Basis for Relief:

AlternateExamination(s):

Surface and volumetric inspection of 7.5 percent, butnot less than 28 welds, of all non-exempt CategoryC-F-1 welds per Code Case N-408, Table 2500-1,Category C-F-l, Item C5.11.

These welds are inaccessible for volumetric andsurface examination because they are located underwater in the suppression pool. Since they are on pumpsuction piping, which is under water, postulatedcracks in these welds are not detrimental to thesafety function of their associated systems.Structural integrity of these welds was demonstratedduring fabrication and erection under ASME Section III.Class 2 welds are selected for examination based onthe selection process found in Code Case N-408. Forstainless steel welds, (Category C-F-l), this codeCase requires that 7.5% of all stainless welds or aminimum of 28 shall be selected. Since there are only36 Class 2 welds of this type, 28 are required per theCode Case. However, 20 are inaccessible as statedabove, therefore, only 16 welds can be examined. Thisrepresented 44 percent of the total C-F-1 populationwhich far exceeds the 7.5 percent selection criteriafor Class 2 piping welds.

Volumetric and surface examinations will be performedon all accessible category C-F-1 welds.

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Section IAppendix F

Page 16Rev. 1

Components(s):

RELIEF REQUEST NO. RR-IWB-4

Miscellaneous Main Steam and Feedwater piping integralattachment to supports.

Welds:

Class:

2FNS-47-13-FN312, 313, 314, 3152FWS-47-14-FW304, 305, 306, 3072FWS-47-18-FN300, 301, 302, 303, 304,2MSS-01-13-FN320, 321, 322, 323, 324,329, 330, 3312MSS-01-14-FN320, 321, 322, 323, 334,2MSS-01-15-FH310, 311, 312, 313, 314,321, 322, 323, 332, 333, 334, 3352MSS-01-16-FW308, 309, 310, 311, 312,325, 526, 332, 334, 336, 338

305325, 326, 327, 328

335, 336, 337315, 316, 317, 320,

313, 314, 315, 324,

ExaminationRequirement(s):

Basis for Relief

AlternateExamination(s):

Volumetric or surface examination is required for allpiping integral attachment welds greater than 5/8" basematerial design thickness, per Table IHB-2500-1, CategoryB-K-l, Item 810.10.

The accessibility for examination of these integralattachment welds is limited to approximately 75 percentof the required weld examination area due to permanentinterferences. The affected welds and associatedinterference is contained in Table 1. The integrity ofthese welds was verified by nondestructive

examination'uring

erection under ASME Section III.In order to fully comply with the Section XI requirementswould require redesign or an unusual large quantity ofmanhours without a compensating increase in the level ofquality or safety.

The required surface or volumetric examinations will beperformed to the maximum extent possible.

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Section IAppendix F

Page 17Rev. 1

RELIEF REQUEST NO. RR-IHB-4 (Cont'd)

TABLE 1

Weld Number

2FHS-47-13-FW312 through 3152FWS-47-14-FH304 through 3072FHS-47-18-FW300 through 3052MSS-01-13-FW320 through 3232MSS-Ol-13-FW324 through 3312MSS-01-14-FH320 through 3232MSS-01-14-FH334 through 3372MSS-01-15-FW310 through 3172MSS-Ol-15-FH320 through 3232MSS-Ol-15-FH332 through 3352MSS-01-16-FH308 through 3152MSS-01-16-FH324 through 3272MSS-01-16-FH332, 334, 336, 338

Interference

Permanent PlatePermanent PlatePermanent PlatePermanent ClampPermanent PlatePermanent PlatePermanent PlatePermanent ClampPermanent PlatePermanent ClampPermanent ClampPermanent PlatePermanent Plate

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Section IAppendix F

Page 45Rev. 1

Components(s):

Class:

Function:

RELIEF REQUEST NO. RR-IWB-12

All valves > 4" nominal pipe size. (See Table 1)

Various

ExaminationRequirements(s):

Basis for Relief:

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Perform visual examination (VT-3) on the internalsurfaces of one valve body in each group of valves of thesame constructional design and manufacturing method thatperforms similar functions in the system per TableIWB-2500-1, Category B-M-2, Item B12.50.

The NMP2 Class 1 systems contain 78 of these valves.These valves have been divided into 35 groups based onsimilar functions and the same design and manufacturingmethod. The specific valves and groups are contained inTable l. If examinations were performed in accordancewith the Code, 35 Valves would be required to bedisassembled for inspection each interval.

The requirement to disassemble primary system valves forthe sole purpose of performing a visual examination ofthe internal pressure boundary surfaces has only a verysmall potential of increasing plant safety margins and a

'erydisproportionate impact on expenditures of plantmanpower and radiation exposure. Furthermore, performingthese visual examinations on poor as cast surfacesprovides little additional information as to the valvebody integrity.

For approximately 20 percent of these valves, the reactorvessel core must be completely unloaded and the vesseldrained to permit disassembly for examination.

The performance of both carbon and stainless cast andforged valve bodies used to construct these valves hasbeen excellent in all BWR applications. Based on thisexperience and both industry and regulatory acceptance ofthese alloys, continued excellent service performance isanticipated.

A more practical approach, that would essentially providean equivalent sampling program and significantly reducedradiation exposure to plant personnel, is to inspect theinternal pressure boundary of only those valves thatrequire disassembly for maintenance purposes. This wouldstill provide a reasonable sampling of primary systemvalves and give adequate assurance that the integrity ofthese components is being maintained.

Section IAppendix F

Page 46Rev. 1

AlternateExamination(s):

RELIEF REQUEST NO. RR-I WB-12 (Cont ')When a valve within a particular valve grouping isdisassembled for maintenance purposes, the internalpressure boundary surface of the valve body will beexamined to meet the Section XI requirement for thatgroup of valves. The valve maintenance procedure willaddress the need for this examination.

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Section IAppendix F

Page 47Rev. 1

RELIEF REQUEST NO. RR-IWB-12 (Cont'd)

TABLE 1

Valve No2CSH*NOV1072CSH*AOV1082CHS*HCV1202CSL*NOV1042CSL*AOV1012CSL*HCV1172FWS*NOV21A2FWS*MOV21B2FWS*AOV23A2FWS*AOV23B2FWS*V12A2FWS*V12B2FWS*HCV54A2FWS*HCV54B2 ICS*MOV1212ICS*MOV1282ICS*AOV1562ICS*AOV1572 ICS*NOV1262MSS~PSV1202NSS*PSV1212NSS*PSV1222NSS*PSV1232MSS~PSV1242NSS"PSV1252MSS*PSV1262MSS*PSV1272MSS*PSV1282MSS*PSV1292NSS*PSV1302MSS*PSV1312MSS*PSV1322MSS*PSV1332MSS*PSV1342NSS*PSV1352MSS*PSV1362NSS*PSV1372NSS*AOV6A2MSS*AOV6B

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Valve No.2MSS*AOV6C2MSS*AOV6D2MSSAAOV7A2MSS*AOV7B2NSS*AOV7C2NSS*AOV7D2MSS*MOVlll2NSS"MOV1122MSS*MOV2072RCS~MOV10A2RCSAMOV10B2RCS*MOV18A2RCS*MOV18B2RCS*HYV17A2RCS*HYV17B2RHS*HCV54A2RHS*HCV54B2RHS*AOV39A2RHS*AOV39B2RHS*MOV40A2RHS*MOV40B2RHS*MOV1122RHS*MOV1132RHS*HCV53A2RHS*HCV53B2RHS*HCV53C2RHS*AOV16A2RHS*AOV16B2RHS*AOV16C2RHS*MOV24A2RHS*MOV24B2RHS*MOV24C2RHS"V1432RHS*MOV1042RHS*HCV1312WCS*MOV1022WCS*MOV1122WCS*MOV1032WCS*MOV200

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