ML20126M418

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Safety Evaluation Concluding Third 10-yr Interval ISI Program Plan,W/Addl Info Provided & Specific Written Relief, in Compliance w/10CFR50.55a(g) & Acceptable
ML20126M418
Person / Time
Site: Millstone Dominion icon.png
Issue date: 01/05/1993
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20126M409 List:
References
NUDOCS 9301080295
Download: ML20126M418 (12)
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4 SAFETY EVALUATIg1 BY THE OFFICE OF NUCLEAR REACTOR REGULATION i

0F THE THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN NORTHEAST NUCLEAR ENERGY COMPANY ,

MILLSTONE NUCLEAR POWER STATION. UNIT 1 1

DOCKET NO._50-245

1.0 INTRODUCTION

Technical Specifications for Millstone Nuclear Power Station, Unit 1, state that inservice inspection (ISI) and testing (IST) of the American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(1). The Code of Federal Regulations in 10 CFR 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized if (1) the proposed alternatives would provide an acceptable level of quality and safety, or (2) compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.

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 each ten-year interval 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 12 months prior to the start of the 120-month inspection interval, 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 its facility, informatica shall be submitted to the Commission in support of that determination and a request made for relief from the ASMC Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(1), the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life, property, or the common defense and security, and are otherwise 9301080295 930105 5 PDR ADOCK 0000 ,

t in the public interest, giving due consideration to the burden upon the-licensee that could result if the requirements were imposed.

The licensee, Northeast Nuclear Energy Company (NNECO), has prepared the Millstone Nuclear Power Station, Unit 1, Third Ten-Year Interval ISI Program Plan to meet the requirements of the 1986 Edition of Section XI of the ASME Boiler and Pressure Vessel Code, except that the extent of examination for Class 1, Examination Category B-J welds has been determined by the requirements of the 1974 Edition, through Summer 1975 Addenda, as permitted by 10 CFR 50.55a(b). The NRC staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has evaluated the Millstone Nuclear Power Station, Unit 1, Third Ten-Year Interval ISI Program Plan, additional information related to the Program Plan, and the requests for relief from certain ASME Code requirements determined to be impractical for Millstone Nuclear Power Station, Unit 1, during the third inspection inte mal.

2.0 EVALVATIEi The ISI Program Plan 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 prior ISI commitments made by the licensee, (e) correctness of the application of system or component examination exclusion criteria, and (f) adequate information in support of requests for relief from certain Section XI code requirements deemed impractical by the licensee.

The information provided by NNECO in support of the requests for relief from certain Section XI requirements has been evaluated and the bases for granting relief from those requirements documented in INEL Technical Evaluation Report EGG-MS-10306. We concur with the findings and recommendations contained in the subject report except for the. recommendation that the Program Plan be found unacceptable because of the-licensee not addressing the issues described in Standard Review Plan Section 3.6.2 and Branch Technical Position MEB 3-1.

Table 1 presents a summary of the reliefs requested and the status of the requests as determined by the staff.

3.0 LONCLUSION The staff concludes that the Millstone Nuclear Power Station, Unit 1, Third Ten-Year Interval ISI-Program Plan, with the additional information provided and the specific written relief, is-in compliance with 10_ CFR 50.55a(g), and is therefore acceptable.

For Requests for Relief B-A-1 (Rev.-1), B-G-1-1, B-G-2-1, C-C-1 (Rev. 1), and IWC-1, it is concluded that NNECO has not provided adequate information to support the determination that the Code requirement is impractical and that l requiring NNECO to comply with the Code requirement would not result in

! hardship. .Therefore, relief is denied.

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For Requests for Relief B-P-1, C-H-1, and C-H-2, it is concluded that relief -

is not required. Requests for Relief D-B-2, 0-B-3, 0-B-4, and D-C-1 were withdrawn-by NNECO and deleted from the ISI Program Plan.

Pursuant to 10 CFR 50.55a(a)(3)(1),- it is concluded that for Requests for Relief IWA-1, IWC-2, and IWF-1, NNEC0's proposed alternatives provide an acceptable level of quality and safety in lieu of- the Code-required examination. In those cases, it is recommended that the proposed alternative be authorized. In the case of Request for Relief IWB-1 and 0-B-1 (Rev.1) it '

is concluded that the proposed alternative is authorized with the conditions stated in the INEL Technical Evaluation Report, pursuant to 10 CFR 50.55a(a)(3)(1).

For all other relief requests evaluated in this document and the associated Technical Evaluation Report, it is concluded that, pursuant to 10 CFR 50.55a(g)(6)(1), relief is granted as requested, except for Requests for Relief B-J-1, B-L-2-1, and B-M-2-1, where relief is granted with the conditions stated in the INEL Technical Evaluation Report. The staff has determined that certain Section XI_ required inservice inspections cannot be performed to the full extent required by Section XI. The NRC staff has determined that granting relief, pursuant to 10 CFR 50.55a(a)(3)(1) and (g)(6)(i), is authorized by law and will not endanger life, property, or the common defense and security and is otherwise in the public interest, giving due consideration to the burden upon NNECO that- could result if the ASME Code requirements were imposed on the facility.

Principal Contributor: David Smith Date: January 5, 1993 i

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l Millstone Nuclear Powe- Station, Unit 1 Page 1 of 7 Third 10-Year ISI Interval TABLE I

SUMMARY

OF RELIEF REQUESTS edief Retief' Respired . auspamot 9ysteur or ' Exam Itaus Regtast . Licarmee W Alternative ._ Status

Categoey . Do. ' Voltame or Area to be Exeurined Method puuber r w t-shett-to-flange Weld VFAC- Volumetric Examination of entire weld Denied 8-A f Reactor B-A 81.30 exam will be perforsed durins Rev. 1 Pressure third inspection period.

vesset' Noz2te-to-vessel Welds RRAD-1, Volumetric Mone. The Code-required eman Granted B-D-1 Rescror 8-D 83.90 RRBD-1, RRCD-1, RRDD-1,' RRED-1, exam will be performed to the Rev. 1 Pressure. extent practicet.

Yessel RRFD-1, RRGD-1, RRHD-1, RRJD-1, RRKD-1, RCAD-1, RC80-1, CSAD-1, CS80-1, TWAD-1 & 2, FWBD 1 & 2, JPAD-1, JPSD-1, CRDD-1, MSAD-1, MS80-1, MSCD-1, MSDD-1, ICAD-1, ICSD-1, HSAD-1, HIAD-1, and M180-1 surface esem VT-1 visual exas Denied 8-G-1-1 Reactor 8-G-1 86.10 RPV closure head nuts Pressure Vesset Insulted bolted connections in high YT-1 visuet none. The Code-required VT-1 Denied B-G-2-1 Class 1 Piping 8-G-2 87.50 visunt exam will be performed 87.70 radiation eress exam Rev. 1 and Valves edien components disessembled for maintenance O

Millstone Nuclear Power Station, Unit 1 Page 2 of 7 Third 10-Year ISI Interval TABLE 1

SUMMARY

OF RELIEF REQUESTS Retlef actief ReryJest System or Exaar Itesa te@ fred Re p eat Number Component Category No. Volume or Aree to be Exonsined feethod Licenace Prepseed Attemative Stattas 8-J-1 Class 1 Piping 8-J 89.11 Containment penetrations in the Surface and None. The Code-required Granted following systems: volt.netric surface exas will be with exams perforsed if the weld is made conditions System Weld Nuter accessible due to repair or stated in CORE.SPR (A)n-16A & (B)X-168 replacement. The VT-2 visual TER FEED.WTR (A)K-9A & (8)X-94 exam will be performed each ISOC. RET (8)X-118 & (A)X-10A intervet.

LPCI (A)M-43 & (B)M-45 MAIN.STM (A)X-7A, (8)X-78, (C)X-7C, (D)M-7D, 1 (E)X-8 RWC11.SUP (8)M-15 & (A)X-14 5HUTCOOL (A)X-12 8-J-2 class 1 Pipins B-J 99.31 Branch connection welds: Surface and None. The Code-required Granted volunetric vett. metric exam wit t be MSAJ-RV1 thru -RV7 exam performed to the maximus MS8J-RV1 thru -RV3 extent practical and along MSCJ-RV1 thru -RV3 with a 100% surface exam MSDJ-RV1 thru -RV6 RCAJ-P81 thru -P82 RCBJ-PS1 thru -PS2 SCAJ-CU1 8-L-2-1 Reactor 8-L-2 e12.20 Punp casing internal surfaces VT-3 visunt mone. The Code-re w ired Granted Coolant exam visual exam will be performed with Recirculation if a pimp is disasseneted for conditions Ptrips maintenance stated in TER 9

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Millstone Nuclear Power Station, Unit 1 Page 3 of 7 Third 10-Year 151 Interval TABLE 1 '

SUMMARY

OF RELIEF REQUESTS r

i

Relief . .

. Relief'- >

Respiest -Systne or .~ Emass Item . ... ., .

- Roepaired Baupseet 1 Busber r=parumt Category llo.' ;  : Volume or Arse to be Emmenited - seethod Licanese Preposed Attornettve Statum-

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lB-M-2-1 Class 1 vetves 8-M-2 812.50 vetve body internet surfaces: VT-3 visuet mone. The Code-required . Granted .

1-FW-9A & B 1-FW-10A & B enas visual exam will be perfonned with 1-LP-11A & B 1-CS-6A & 8 when a valve is disassen6ted conditions; 1-CD-29 1-RR-1A & 8 for maintenance stated in 1-LP-10A & 8 1-!C-1 & 2 TER 1-50-1 & 5 1-CS-7A & 8 1-CS-5A & 8 1-IC-3 & 4 ,

1-RR-2A & 8 1-at-4A & W 1-LP-12A & B 1-FW-11A & B 1-SD-2A & 3 1-MS-1A, 8, C, & D i 1-MS-2A, B, C, & D 1-MS-3A, 8, C, D, E, & F 1-CU-1, 2, 3, 5, 28 1 30 t P-1 RPV, Ctess 1 B-P 815.11 Reactor verset and closure head, Hydrostatic System teoksee test in Relief not Rev. 1 Piping, Ptmps 815.51 head sprey e,d vene, reactor test per accordance with ASME Code rewired and valves 815.61 recirculation, main steem, IWB-5222 Case n-498 815.71 -feedwater, stan @y liquid control, '

tow pressure coolant injection, i

' core spray, isolation condenser,  ;

reactor shutdown cooling, reactor i water clean-te , control rod drive, ,

and reactor pressure instrtsnentation systems.

IWB-1 Ctoss 1 Additlonal examinstion requirements IWB-2430 Additionet ==ema of equal Authorized Systeas for a1L C1 ass 1 componmta number of afsiLer cagxments uIth within inspection item number condittens ,

stated in'  !

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M111 stone' Nuclear Power Station, Unit'l Page 4 of 7 ,

Third 10-Year ISI Interval TABLE 1

SUMMARY

OF RELIEF REQUESTS f metlef cellef -

R=p a== t Systen or- Eaan --- Item -- . .

- Seedred . .

amupsmat .

Bumber Camponent Category . no. - Wolume or Area to be Esamined Method ' Licaname Praguesad Attornstlwe' Status C-A-1' Low Pressure C-A C1.30 Tubesheet-to-shett welds on the voltsmetric 1 1/2 vee path scan from one Granted.

Rev. 2 Coolant following LPCI heat exchangers; exam side to extent practical and Injection 100% surface exam of welds (LPCI) Heat. 'CCAC-A-1 CCAC-A-2 Exchanger CC8C-A-1 CC8C-A-2 C-8-1 Isolation C-8 C2.21 Nozzle-to-shett (or head) Welds surface and Wene. The Code-required Granted Condenser- ICAC-8-1, ICAC-8-2, IC8C-8-3, and volumetric voltanetric exam will be

'ICBC-8-4 exams performed to extent practical and 100% surface exam C-8-2 Shutdown C-8 C2.21 Nozzle-to-shett Welds SDAC-8-1 Surface and None. Code-reg ired Granted Cooting Meat 'SD8C-8-1, SOAC-8-2 and SDBC-8-2 volumetric vettmetric exam will be Exchanger- exams performed to exten* practical and 100% surface exam C-C-1 Class 2- C-C C3.20 Integrally welded attachments to surface exam Atternate selection criteria Denied Integralty piping Wetded Attachments CEM-1 Class 2 C-H C7.20 Pressure ressels, p m , valves, Hydrostatic System teakage test per ASME Relief not Rev. 1 Pressure C7.40 ~and piping in the main steam, test per code case N-498 re wired Retaining C7.60 condensate, condensate booster IWC-5222-Components C7.80 feedwater, emergency. condensate .

transfer, stanchy liquid control, t LPCI, core spray,, isolation condenser, reactor shutdown cooling ,

and scram systems 1 e

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b Millstone Nuclear Power Station, Unit 1 Page 5 of 7 i Third 10-Year ISI Interval ->

TABLE I L

SUMMARY

OF RELIEF REQUESTS ,

Relief I .

~ Relief-

. Request  ? System or  : Exam '. Item . . . . . _ .. -: . Required .

Request '

sksuber Compnnent: Category ' No. .- , Volume or Aree to be Examined ' seethod . . - Licensee Prgesed Attemative ' - Statum -

C N-2 Class 2 Piping C-N ' C7.40 Primary containment piping Hydrostatic System teakage test per ASPE Relief not f penetrations: test per. Code Case N 498 ' required  !

IWC-5222  :

Station Air Stpply to the drywett; i Drywett floor and equipment drain i supps; [

Drywell Demineralized Water Stpply; i Transversing incore Probe and [

Nitrogen Purge Tubing; i forus Pressure and Water Levet [

. Instrumentation; and . ,

Drywelt Nitrogen Compressor Suttion i J

and Discharge. l IWC-1 Class 2 C-A Pressure vessets, nozzle-to-vessel Surface None, Paragraph IWC-1220(c) Denied t

'wetds,: integral attachments and esenption criteria of 74S75

~

Feedwater C-8 and/or I Coolant- C-C welds in carbon or low attoy steet volunetric Code. 'l injection C-t-2 piping. exam '

(FUCI) System IWC-2 Class 2. Additional examinations for att IWC-2430 Additionat exams of similar Authorized l Systems Class 2 conponents. components equet in ramber-to .. !

20% of welds scheduled in 5 a

Intervat for inspection Item -

Nts@er D-B-1 Class 3 D-8 02.20 . Integrat attachments of coeponent VT-3 visuat VT-3 visunt exam of 10% of Authorized' Rev. 1 .Integrat D2.40 stports, restraints, and spring exam- integral attaciunents. with Attachments type supperts. conditions stated in

. TER : ,

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Millstone Nuclear. Power Station, Unit 1 Page'6 of 7 Third 10-Year ISI Interval--

TABLE 1

SUMMARY

OF RELIEF REQUESTS ..

i

' Relief 1 . ..

T Se4lef '  ;

Respast Systne or . - Enam : Item: , .. , . . . . Souprired .

Sagast "t Ikeuber Component ' Category- No, TVoltme er Arge to be Enemined - 90ethod Licensee Preposed A(tomotive Status j

.i D-8-2 Emergency D-B D2.10 Withdraun l Service rater- in 11/5/91- ,

System _ tetter  !

D-B-3 Reactor D-B - D2.10. Withdream Building in 11/5/91 ,

closed Loc 41ng tetter  ;

Water D-B-4 Turbine D-B D2.10 Withdraun Sullding in 11/5/91 Secondary letter Closed CootIng Water ,

i D-B-5 Main Steam D-B Automatic Pressure / Steam Relief Pneumatic Remote /menuel actuation of Granted APR/SRV' Valve (APR/SRV) discharge piping test per APft/SRV valve to confirm open l Discharge into torus / suppression chamber IWD-5223(f) flou path Piping D-B-6 Stan &y Gas D-B~ 02.10 Pressure retaining components Hydro test System flow test per Granted Treatment per Millstone, Unit 1 Technical System IWD-5723: Specification 4.7.3.1.A and ftnetionet secondary containment test per tightness test 1w-5222 D-C 1 Fuel Pool D-C ' D3.10 Pressure retaining components . Withdrawn Cooling System in 11/5/91 Letter

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Millstone Nuclear Power Station, Unit 1 Page 7 of 7 Third 10-Year ISI' Interval TABLE I

SUMMARY

OF RELIEF REQUESTS Relief' metief RegJest System or Ensu ' Item .

Souprired .

Regisest

~

ihmber Caponent Category. so. Votiser'or Area to be Emmoined stethod ..Licarmee Propeesd Attornetive Stetta IWA-1 oualifications of nondestructive IWA-2300(e) weer-distance vision test Authorized testing personnet requirements of A9EE Code case N-490 IWF-1 Class 1, 2, F-A F1.10 component supports VT-3 visual VT-3 visuel exam in Authorized and 3' F-8 thru exam eccordance with ASME Code Camponent F-C F3.50 case N-491 S p rts IWF-2 Mechanicet and Inservice Testing Fmettonal IWF-5400 mot Hydraulic - evaluated Sntbbers in this report i

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