ML17056B110

Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan

ML17056B110
Person / Time
Site:	Nine Mile Point
Issue date:	11/01/1990
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML17056B109	List: ML17056B108 ML17056B110
References
NUDOCS 9011190053
Download: ML17056B110 (24)

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NUCLEAR REGULATORYCOMMISS)ON WASHINGTON, O. C. 20555 ENCLOSURE =1 SAFETY EVALUATION-BYTHE OFFICE OF NUCLEAR REACTOR REGULATION FIRST TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410

1. 0 INTRODUCTION Technical Specification 4.0.5 for the Nine Mile Point Nuclear Station, Unit 2, states that the surveillance requirements for Inservice Inspection and Testing of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Class 1, 2, and 3 components shall be applicable as follows:

Inservice Inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Code and applicable Addenda as required by 10 CFR Part 50,,Section 50.55a(g),

except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(i).

Pursuant to 10 CFR 50.55a(g)(4),

ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components,"

to the extent practical within the limitations of design,

geometry, and materials of construction of the components.

The regulations require that inservice examination of components and system pressure tests conducted during the first ten-year interval shall comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) on the date twelve months prior to the date of issuance of the operating license, subject to the limitations and modifications listed therein.

The components (including supports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein.

Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for their facility, information shall be submitted to the Comission in support of that determination and a request made for relief from the ASME Code requirement.

After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i), the COImission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life or property or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.

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<<2-On July 30, 1987, Niagara Mohawk Power Corporation (the licensee) submitted the First Ten-Year Interval Inservice Inspection (ISI) Program Plan, Revision 0, for 'the Nine Mile Point Nuclear Station, Unit 2, to meet the requirements of the 1983 Edition, Summer 1983 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code.

The staff, with technical assistance from its contractor, Idaho National Engineering Laboratory, has evaluated the First Ten-Year Interval Inservice Inspection Program Plan, Revision', additional information submitted on February 12, 1988, related to the plan, and the requests for relief from certain ASME Code requirements determined to be impractical to perform at the Nine Mile Point Nuclear Station, Unit 2, during the first inspection interval.

By letter dated May 19, 1989, the licensee submitted Revision 1 to requests for relief (RR-IWB-4, RR-IWB-6, RR-IWC-4, RR-IWC-2, RR-IWB-12) from ASME Code requirements which the licensee has determined to be impractical for the first 10-year inspection interval.

Corrections to Request for Relief RR-IWB-4 were provided in a letter dated February 27, 1990.

2. 0 EVALUATION The ISI Program Plan submitted on July 30, 1987, and modified by letters dated February 12,

1988, May 19,

1989, and February 27,

1990, has been evaluated for (a) application of the correct Section XI Code edition and addenda, (b) compliance with examination and test requirements of Section XI, (c) acceptability of the examination

sample, (d) compliance with commitments made by the licensee prior to plant operation, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information in support of requests for relief from impractical Section XI Code requirements.

The ISI program and the requests for relief (RR) have been reviewed by the NRC staff with the assistance of its contractor, EGKG Idaho, Inc.

The enclosed Technical Evaluation Report (TER) is EG&G's evaluation of the licensee's program and relief request submittals of July 30, 1987 and February 12, 1988.

The staff has reviewed the TER and concurs with the evaluation and conclusions contained in the TER subject to the later revisions to RR-IWB-4, RR-IWB-6, RR-IWB-12, RR-IWC-2, and RR-IWC-4.

The staff has determined that the licensee's ISI Program Plan as revised, with the exception of Relief Request RR-IWB-13, which is denied, reflects compliance with the requirements listed above.

A summary of the relief requests and action taken is contained in Table 1.

Revised Relief Requests IWB-4, IWB-6, IWB-12, IWC-2, and IWC-4 are discussed below.

Relief Re uest RR-IWB-4 Rev.

1:

Weld 2MSS-01-16-FW332 was added to the list o

a n

earn an ee wa er psping integral attachment welds which are partially inaccessible for the Code-required, surface examination due to permanent inter-ferences.

The limited surface examination (approximately 75% of the required surface) of these integral attachment welds will provide reasonable assurance of the continued inservice structural integrity.

The evaluation of this relief

request, as submitted on July 30, 1987, granted the relief requested.

Therefore, the disposition of this relief request remains unchanged with relief granted as requested.

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Relief Re uest RR-IWB-6 Rev. I:

As a result of the staff's initial review, re e

was e erm ne no o

e appropriate for the pipe-to-sweepolet (reactor coolant system) welds listed fn Revision 0 of this relief request.

Relief was found to be appropriate for the remaining welds fn Revision 0.

In Revision 1, the licensee has deleted the reference to the pipe-to-sweepolet welds.

Therefore, only the welds for which relief would be appropriate are listed fn Revision 1

of the relief request and relief is granted for RR-IWB-6, Rev. I, as requested.

Relief Re vest RR-IWB-12 Rev..l:

This relief request was revised to reflect t e rep acemen o t e a

n team Isolation Valves (valves 2MSS*HYV6A, 6B, 6C, 6D, 7A, 7B, 7C, and 7D were replaced with valves 2MSS+AOV6A, 6B, 6C, 6D, 7A, 7B, 7C, and 7D).

The licensee's commitment to perform the required visual examination of the internal pressure boundary surface of the valve body whenever a valve within a particular group of valves is disassembled for maintenance is acceptable.

Disassembly of a valve for the sole purpose of inspection fs impractical.

The evaluation of this relief request as submitted on July 30, 1987, granted the relief requested.

Therefore, the disposition of this relief request remains unchanged with relief granted as requested.

Relief Re uest RR-IWC-2 Rev. I:

Weld 2CSH-25-05-FW015 was added to the list o

es ua ea emova an ore Spray system stainless steel piping welds which are inaccessible for the Code-required volumetric and surface examinations.

It fs impractical to perform the Code-required volumetric and surface examinations of these welds because they are submerged in the suppression pool.

The evaluation of the relief request as submitted July 30, 1987, granted the relief requested.

Therefore, the disposition of this relief request remains unchanged with relief granted as requested.

Relief Re uest RR-IWC-4 Rev. I:

This relief request was revised to incorpora e supp emen a

sur ace examinations of the integral attachment welds.

The magnetic particle and liquid penetrant examinations of these welds provide reasonable assurance of the continued inservice structural integrity.

The evaluation of this relief request as submitted on July 30, 1987, granted the relief requested.

Therefore, the disposition of this relief request remains unchanged with relief granted as requested.

3.0 CONCLUSION

The staff concludes that the Nine Mile Point Nuclear Station, Unit 2, First Ten-Year Interval Insevfce Inspection Program Plan, Revision I, with the additional information provided and the specific written relief (excluding IWB-13 for which relief is denied) constitute the basis for compliance with 10 CFR 50.55a(g) and Technical Specification 4.0.5 and fs therefore acceptable.

The staff has determined that pursuant to 10 CFR 50.55a(g)(6)(i) and (a)(3)(i), granting the relief described in Table 1 is authorized by law and will not endanger life or property or the common defense and security and that granting the relief is otherwise in the public interest considering the burden that could result if the requirements were imposed on the facility.

Dated:

Prfnci al Contributor:

eorge o nson

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RELIEF RE(UEST NUMBER ITEM NO.

EXAM CAT.

TABLE 1 VOLUME OR AREA TO BE EXAMINED

SUMMARY

OF RELIEF REQUESTS SYSTEM OR COMPONENT...

RE(VIREO METHOD ENCLOSURE 2-LICENSEE

'ROPOSED ALTERNATIVE RELIEF R.EQUEST STATUS RR-IWB-1 B.14.10 B-0 Reactor Pressure Vessel (RPV)

Pressure Retaining Welds in Control Rod Housings Volumetric or Surface-100K of IOX of the peripheral CRD housing welds Partial exam of 10% of the welds plus five addi-tional welds Granted RR-IWB-2 B3.90 B-D RPV RPV nozzle to shell Welds:

2RP V-KAOl 2RP V-KA18 2RPV-KA02 2RPV<<KA19 2RPV-KA03 2RPV-KA20 2RPV-KA04 2RPV-KA21 2RPV-KA05 2RPV-KA22 2RPV-KA06 2RPV-KA23 2RPV-KA07 2RPV-KA24 2RPV-KAOB 2RPV-KA25 2RPV-KA09 2RPV-KA26 2RPV-KA10 2RPV-KA32 2RPV-KA11 2RP V-KA12 2RP V-KA17 100K volumetric VT-1 exam will be performed on por-tions which cannot be inspected by volumetric methods Granted RR-IWB-3 01.11 8-A RPV Pressure Retaining Shell Welds:

100K volumetric Perform Examina-tion to Maximum Extent Possible Gran~;"-:.-',

B1.12 2RPV-AA 2RPV-AB 2RPV-BA 2RPV-BB 2RPV-BC 2RPV-BD 2RPV-BE 2RPV-BF 2RPV-AC 2RPV-AD 2RPV-BG 2RPV-BH 2RPV-BJ

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NINE MILE POINT UNIT 2 PAGE 2 of 9

SUMMARY

OF RELIEF REQUESTS TABLE 1 RELIEF REQUEST NUMBER ITEM EXAM NO.

CAT.

SYSTEM OR COMPONENT VOLUME OR AREA TO BE EXAMINED REQUIRED METHOD LICENSEE PROPOSED ALTERNATIVE RELJEF REQUEST STATUS RR-IWB-7 B1. 22 B-A RPV Circumferential and 100K volumetri c Meridional Head Welds=

and Head-to-Flange Welds:

Perform Examina-tion to Maximum Extent Possible Granted B1.21 B1.40 RPV-DA RPV-DB RPV-DC RPV-DG RPV-DR RPV-AG RPV-DD RPV-DE RPV-DF RR-IWB-13 B6.30 B-G-1 Reactor Pressure Vessel Closure Studs, when removed 1005 surface and volumetric VT-1 visual exam Denied in lieu of surface RR-IWB-4, 810.10 Rev.

1 (5/19/89) 8-K-1 Hain Steam and Feedwater System supports Integral Welded Attachments to supports:

100K Volumetric None or surface exam Granted Weld Numbers 2RIS-TTPFPIIF' gh 315 2FWS-47-14-FW304 through 307 2FWS-47-18-FW300 through 305 2MSS-Ol-13-FW320 through 323 2MSS-Ol-13-FW324 through 331 2MSS-01-14-FW320 through 323 2MSS-01-14-FW334 through 337 2MSS-Ol-15-FW310 through 317 2MSS-Ol-15-FW320 through 323 2MSS-01-15-FW332 through 335 2MSS-01-16-FW308 through 315 2MSS-01-16-FW324 through 327 2MSS-01-16-FW334, 336, 338 2MSS-01-16-FW332

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NINE MILE POINT UNIT 2 PAGE 3 of 9 RELIEF REQUEST NUMBER ITEM EXAM NO.

CAT.

SYSTEM OR COMPONENT TABLE 1

SUMMARY

OF RELIEF REQUESTS VOLUME OR AREA TO BE EXAMINED REQUIRED METHOD LICENSEE PROPOSED ALTERNATIVE RELIEF REQUEST STATUS RR-IWB-5 (Part 1 of 2)

B5.10 B-F Reactor Pressure

. ft Vessel Nozzle-to-Safe End Wel d:

-RPV-KB-13 100K volumetric and surface Volumetric to Granted extent practical; 100% surface B9.11 RR-IWB-6$

B9.11 Rev.

1 (5/19/89)

B-J B-J Piping Pressure Boundary Piping Pressure Boundary Pressure Retaining Circumferential Welds:

2ICS-57-07-FW021 2MSS-01-13-FW007 2MSS-Ol-15-SW014 2MSS-01-15-FW006 Pressure Retaining Welds:

2RCS-64-00-SW003 2RCS-64-00-FWA01 2RCS-64-00-FWA05 2RCS-64-00-FWB01 2RCS-64-00-FWB08 2RHS-66-55-FW001 2WCS-09-05-SW025 2WCS-09-05-SW020 100K volumetric Volumetric to Granted and surface extent practtcaI; 100K surface 100K volumetric Volumetric to Gr anted and surface extent practical; examination 100% surface

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NINE POINT UNIT 2 PAGE RELIEF REQUEST ITEM NUMBER NO.

EXAM SYSTEM OR...

CAT.

COMPONENT TA~

1

SUMMARY

OF RELIEF REQUESTS VOLUME OR AREA TO BE EXAMINED REQUIRED METHOD LICENSEE PROPOSED ALTERNATIVE RELIEF REQUEST STATUS RR-IWB-8 B5.10 B9.11 RR-IWB-9 B5.10 RR-IWB-10 B9.11 B-F Piping Pressure Boundary B-J B-F Reactor Pressure Vessel B-J Piping Pressure Boundary RPV Nozzle-to-Safe End Welds:

RPV-KB29 RPV-KB30 Circumferential Piping Weld:

2-RCS-64-00-FWA06 Nozzle-to-Safe End Welds:

RPV-KB01 RPV-KB17 RPV-KB02 RPV-KB18 RPV-KB03 RPV-KB19 RPV-KB04 RPV-KB20 RPV-KB05 RPV-KB21 RPV-KB06 RPV-KB22 RPV-KB07 RPV-KB23 RPV-KB08 RPV-KB24 RPV-KB09 RPV-KB25 RPV-KB10 RPV-KB26 RPV-KB11 RPV-KB32 RPV-KB12 Circumferential Welds:

2RCS-64-00-FWA17 2RCS-64-00-FWB19 2RCS-64-00-FWA21 100K volumetric Perform Volumetric Granted and surface Exam to Extent Possible; 100$

Surface IOOX volumetric Perform Volumetric Grantede and surface Exam to Extent Possible;-

lOOX Surface 100K volumetric Perform Volumetric Granted and surface Exam to Extent Possible; 100K Surface Volumetric and lOOX surface and Granted surface volumetr ic to extent practical

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NINE MILE POINT UNIT 2 PAGE 5 RELIEF REQUEST ITEM NUMBER NO.

EXAM SYSTEM OR CAT.

COMPONENT

SUMMARY

OF RELIEF REQUESTS VOLUME OR AREA TO BE EXAMINED REQUIRED METHOD LICENSEE PROPOSED ALTERNATIVE REL.IEF REQUEST STATUS RR-IMB-ll B12.20 B-L-2 Reactor Cool ant

,, Recirculation Pumps Internal Surfaces Visual (VT-3)

Exam to be per-formed when a pump is dis-assembled for maintenance Granted RR-IWB-5 B12.40 (Part 2 of 2)

B-M-1 Valve Pressure Boundary Valve Body Pressure Volumetric Retaining Weld VWHYV7B Volumetric Exam to Extent Possi-ble; Surface Exam Mhen Required Granted RR-IWB-12, B12.50 Rev.

1 (5/19/89)

B-M-2 Valve Pressure Boundary Internal Surfaces of valves:

'MSS+AOV6A,6B,6C, 6DU7As7Bs7Cs

> 7D Visual VT-3 Visual when valve'ranted is disassembled for maintenance RR-IWC-5 C1.10 (Part 1

of 3)

C1.20 C2.21 C2.22 C-A C-A C-B C-B Pressure Vessel Pressure Vessel Pressure Vessel Pressure Vessel Pressure Retaining Weld:

HW-101A Pressure Retaining Meld:

HW-100A Pressure Retaining Melds:

HW-102A HW-103A Pressure Retaining Melds:

HM-105A Volumetric Volumetric Surface and Volumetric Volumetric Perform to Maximum Granted Extent Possible Perform to Maximum Granted Extent Possible Perform to Maximum Granted Extent Possible Perform to Maximum Granted Extent Possible

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RELIEF REQUEST NUMBER ITEM NO.

EXAM CAT.

SYSTEM OR COMPONENT

SUMMARY

OF RELIEF REQUESTS VOLUME OR AREA TO BE EXAMINED REQUIRED METHOD LICENSEE PROPOSED ALTERNATIVE RE'. ='-':,=

S TAP~".

RR-IMC-2, C5.11 Rev. )

(5/19/89)

RR-IWC-3 C3.20 C-F-1 C-C Stainless Steel or High A11oy Piping Pressure Retaining Melds:-

2CSH-25-05-FM012 2CSH-25-05-FM013 2CSH-25-05-FM014 2CSH-25-05-FM015 2CSL-26-Ol-FM026 2CSL-26-01-FW027 2CSL-26-OI-FM028 2CSL-26-01<<FW035 2RHS-66 FW023 2RHS-66-13-FW024 2RHS-66 FM025 2RHS-66-13-FM029 2RHS-66-22-FW021 2RHS-66-22-FW022 2RHS-66-22-FW023 2RHS-66-22-FW029 2RHS-66-23-FM018 2RHS-66-23-FW019 2RHS-66-23-FM029 2RHS-66-23-FW022 Welds on Integrally Melded Attachments to Piping:

26-01-CSL-FM313 26-01-CSL-FW314 Surface and Volumetric Surface Perform Exams on Accessible Melds None Granted Gr ed RR-IMC-4, C3.20 Rev.

1 (5/19/89)

C-C Control Rod Drive System Welds on Integra't ly Wel ded Attachments to Piping:

144 Welds'n Piping Lugs Surface Surface Exam to Granted Maximum Extent Possible

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NINE POINT UNIT.2 PAGE 9

T t.

1 SUHNRY OF. RELIEF REQUESTS I

RELIEF REQUEST NUMBER ITEN NO.

EXAM CAT.

SYSTEM OR COMPONENT VOLUME OR AREA TO BE EXAMINED REQUIRED METHOD LICENSE PROPOSED ALTERNATIVE REL I"--".

REQU.;.'RAN';3 RR-IWC-5 (Part 2 of 3)

C3.20 C-C Core Spray and Residual Heat Removal Systems Welds on Integrally Melded Attachments to Piping:

2CSH-25-09-FW300 2CSH-25-09-FW305 2RHS-66-16-FW304 2RHS-66-.18-FM311 2RHS-66-18-FW312 2RHS-66-20-FW303 2RHS-66-20-FW304 2RHS-66-20-FM305 2RHS-66-20-FW306 2RHS-66-57-FW305 2RHS-66-57-FM306 2RHS-66-57-FW307 Surface Surface Exam to Extent Possible Gran."-:.

C5.11 C5.51 C-F-1 C-F-2 Stainless Steel or High Alloy Piping Carbon or Low Alloy Steel Piping Pressure Retaining Welds in Piping:

2RHS-66-13-FW021 2RHS-66-22-FW019 Pressure Retaining Weld:

2RHS-66-19-SM026 Surface and Volumetric Surface and Volumetric Exams to be Per-Granted formed to Maximum Extent Possible Exaea to be Per-Grant formed to Maximum Extent Possible RR-IWC-1 C3.30 C-C Pumps Integral Attachment Welds for Pumps/

Welds:

2RHS*PIA/[PW121A) 2RHS*PI8/[PM121B1 2RHS*PIC/[PM121C]

Surface Perform Surface Exam on Welds of Pump when Dis-assembled for maintenance Granted 2CSW~P1/[PW220 222eb 2231 2CSL*P1/[PW319

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NINE POINT UNIT 2 PAGE 9

TABLE 1 SU50RY OF, RELIEF REQUESTS RELIEF REQUEST NUMBER 4

ITEM NO.

EXAM CAT.

SYSTEM OR COMPONENT VOLUME OR AREA TO BE EXAMINED REQUIRED METHOD; LICENSE PROPOSED ALTERNATIVE RELIE" REQUE; GRANT"."~

RR-IWC-1 C6.10 C-G Pumps 2RHS*P1A/[PW111A, 112A]

2RHS*P1A/f 2RHS*P1B/[

2RHS*P1B/[

2RHS*P1C/[

2RHS*pjc/[

PW113A, 116A, 118]

PW1110, 1128]

PW113B, 116B, 118B]

PWlllC, 112'W113C,116t.,

118C]

PW207, 208, 209]

PW212, 217, 218, 219]

PW311, 312, 315]

2CSH*P1/[

2CSH*P1/[

2CSL*P1/[

Casing Welds for the Surface following pumps/

welds:

Perform Surface Exam on Welds of Pump when Dis-assembled for maintenance GraN'...-

RR-IWC-5 C6.20 (Part 3

of 3)

C-G Valves Valve Bog Welds:

VWHCV118-C,D VWMOVIC-B, C, D VWMOV2A-A,B,C VWMOV112-B,C,D

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Surface Exams to be Per-Granted

.formed to Maximum Extent Possible

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NINE POINT UNIT 2 PAGE 9

T 1

SUHMARY OF. RELIEF REQUESTS RELIEF REQUEST NUMBER ITEM NO.

EXAM SYSTEH OR CAT.

COMPONENT 'OLUME OR AREA TO BE EXAMINED REQUIRED METHOD LICENSE PROPOSED ALTERNATIVE RELIEF REQUES" GRANT~~~,

4 RR-IWD-1 1.20 1.30 1.40 1.50 1.60 2.20 2.30 2.40 2.50 2.60 3.20 3.30 3.40 3.50 3.60 D-A Class 3 Piping D-B D-C Integral Attachments VT-3 for component sup-ports and restraints for pressure retain-ing piping downstream of last shutoff valve on open ended systems None Grante.'R-IWF-1 F3.50 F-C Component Standard Supports Spring Type supports, VT-4 constant load type

supports, shock ab-

sorbers, and flydrau-lic and mechanical type supports VT-3 Granted 4

4$

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