ML18153A726

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Safety Evaluation Re Third 10-yr Interval Inservice Insp Program Update & Associated Requests for Relief
ML18153A726
Person / Time
Site: Surry 
Issue date: 07/19/1995
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML18151A975 List:
References
NUDOCS 9508040246
Download: ML18153A726 (7)
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20655-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION Of THE THIRD TEN-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF

1.0 INTRODUCTION

.fQB VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT 1 DOCKET NUMBER: 50-280 The Technical Specifications for Surry Power Station, Unit 1 state that the inservice inspection 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 ASHE Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.SSa(g), except where specific written relief has been granted by the Conmission pursuant to 10 CFR 50.55a(g)(6)(i).

10 CFR 50.SSa(a)(l) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) 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), ASHE 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 ASHE 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 and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.SSa(b) on the date twelve months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable edition of Section XI of the ASME Code for the Surry Power Station, Unit 1, third IO-year inservice iQspection (ISi) interval is the 1989 Edition. The components (including iupports) may meet the requirements set forth in subsequent editions and addenda of the ASME Code incorporated by reference in 10 CFR 50.SSa(b) subject to the limitations and modifications listed therein and subject to Commission approval.

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  • Pursuant to 10 CfR 50.SSa(g)(S), if the licensee detennines that conforaance with an examination requirement of Section XI of the ASME Code is not practical for its facility, infonnation shall be.submitted to the Coaaission 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 S0.55a(g)(6)(i), the Co11111ission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life, property, or the conmon 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.

In a letter dated July 16, 1993, Virginia Electric and Power Company (licensee) submitted to the NRC its Third Ten-Year Interval lnservice Inspection Program Plan, Revision O and associated requests for relief for the Surry Power Station, Unit 1. Additional infonnation was provided by the licensee in its letters dated June 22, 1994, September 12, 1994, October 19, 1994, and by teleconference on February 23, 1995.

2.0 EVALUATION AND CONCLUSIONS The staff, with technical assistance from its contractor, the Idaho National.:

Engineering Laboratory (INEL), has evaluated the information provided by the licensee in support of its Third Ten-Year Interval lnservice Inspection (ISi)

Program Plan, Revision 0, and associated requests for relief for Surry Power Station, Unit 1.

Based on the contractor's review of the ISi program, no deviations from regulatory requirements or co11111itments were identified in the Surry Power Station, Unit 1, Third Ten-Year Interval ISI Progra11 Plan, Revision 0.

With respect to the relief requests, the staff adopts the contractor's conclusions and reco11111endations presented in the Technical Evaluation Report attached, with the exception of Request for Relief No. RR 11.

In Request for Relief RR 11, the Code-requirement IWA-5242(a) states that for systems borated for the purpose of controlling reactivity, insulation shall be removed from pressure-retaining bolted connections for VT-2 visual examination.

The licensee has requested relief from the Code-requirement of removal of insulation for VT-2 visual examination of bolted connections in borated systems that are normally tested in sub-atmospheric conditions (Reactor Coolant, Charging, and Safety Injection System).

The licensee ha1 proposed the following alternative examination: *bolted

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connections on Class 1 systems containing boric acid to be examined each refueling outage at zero or static pressure. The examination would be performed w.ith insulation removed.

Class 2 bolting will be examined similarly once a perfod. This alternative only applies to systems that are pressure tested under sub-atmospheric conditions.

In addition the required testing will be conducted with a VT-2 examination without removing the insulation.*

  • The Code**requ1rement to perform a VT-2 with the insulation removed during system pressure testing is impractical for systems under sub-atmospheric conditions. Because Surry, Unit 2 operates with a subatmospheric containaent, compliance with the code requirements would require stat-ion.personnel to reinsulate the lines as well as disassemble and remove scaffolding froa the containment while wearing self-contained breathing apparatus *. Furtheraore, the piping will be at normal operating temperature which will create an additional personnel hazard as well as being exposed to increased radiation levels. Compliance with the Code requirement would result in significant personnel hazard.

Removal of insulation from bolted connections and examination for evidence of boric acid during the refueling outage at zero or static pressure should allow detection of any leaks occurring at the bolted connection. Since the same Code corrective actions would be required, the licensee's proposed alternative should provide adequate assurance of the integrity of these connections. Therefore, in view of the burden on the licensee that could result if the Code requirements were imposed on the facility, the licensee's Request for Relief No. RR 11 is granted pursuant to 10 CFR S0.5Sa(g)(6}(i).

In su11111ary, in view of the burden on the licensee, that could result 1f the Code requirements were imposed on the facility, requests for Relief Nos. 2, I, 7, 8, SR-002, SR-003, SR-004, SR-006, and RR-11 are granted pursuant to 10 CFR 50.55a(g)(6)(i). The proposed alternative for request SR-006 is authorized provided that each Class 1 and 2 piping weld examined receives all of the reference markings at the time of inservice examination to provide assurance of traceability of piping welds and.repeatability of examinations. The relief granted is authorized by law and will not endanger life or property or the connon defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. The alternatives, which provide an acceptable level of quality and safety, contained in Requests for Relief Nos.

3, 5, 10, SR-001, SR-007, and SR-008 are authorized pursuant to 10 CFR S0.55a(a)(3)(i). With respect to Relief No. 10, the proposed alternative is authorized provided that at least one bolt closest to the source of leakage is removed and evaluated. Because compliance with the specified requirement would result in hardship or unusual difficulty without a compensatory increase in the level of quality and safety, the alternative contained in Request for Relief No. SR-005 is authorized pursuant to 10 CFR 50.5Sa(a)(3)(ii). Requests for Reli~f Nos. 4 and 9 were withdrawn by the licensee. Relief is not required for Request for Relief No. SH-1.

By teleconference on February 23, 1995, the licensee stated that it was withdrawing Request for Relief No. RR-1 from its ISi program and will provide documentatiQn to that effect in the near future.

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SURRY POWE~ STATION, UNIT 1 Third 10-Year ISi Interval SR-001 SR-002 R-003 SR-004 SR-005

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Reactor Ve11el Ste*

Generator Pru1urizer Recirc.

Spray and Safety Injection PUllpS Ultra1onlc Calibration Block 1-F 15.10 1-D 13.140 B-D 13.120 C-G C6.10 APP-I II TABLE I

SUMMARY

OF RELIEF REQUESTS Nozzle-to-Safe End Butt Welda Weld No.

Dr.,ing No.

1-01DN 11448-WICNS*0100AZ-1 1-17DN 11448-WICNS-0100AZ-1 1-01DN 11448-WKNS-0101AZ-1 1-17DN 11448-WICNS-0101AZ-1 1-01DN 11448-WKNS-0102AZ-1 1-17DN 11448-W1CNS-0102AZ*1 Nozzle Inside ledlua Sections Nark No.

Caaponent No.

1-01ANIR 1-IC*E-1A 1*011NII 1-IC-E-1A 1-02ANIR 1-IC-E-11 1-02BNIR 1-RC-E-11 1-03ANIR 1-1c-E~1c 1-03BNIR 1-RC-E-1C Surge Nozzle Inside Radius Section All Reactor Coolant Pulp Ca1lng Yeldii PUllpS 1A, 1B, 2A, and 2B Welda 2-01, 2-02, 2-03, and 2-04 Cal lbratlon block fabrication requi raent11 surface and voh.. tric ex*il"llltion Vol~tric ex*ll"llltlon Vohaetric ex*il"llltion Surface

      • ll"llltlon Section XI, Append! X 111 and Section V, Article IV Page I of 4 Lt..-. P1'11p11Md

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Autcaated 100X Authorized voh.. trlc exa fraa the pipe ID surface Vl1ual (VT-1)

...1.... t1on fraa the nozzle ID Visual (VT-2)

      • il"llltlon during prnaure tnt Vl... l (VT-1) ex*ll"llltlon If puap 11 di.. 11aabled and lheft remved for *lntenance Granted Granted W/Condi ti ona Granted U** exl1tlng cal lbratlon Authorized block*

SURRY POWER STATION, UNIT 1 Third 10-Year ISi Interval SR-006 SR-007 SR-008 RR 1 RR 2 RR 3 All ClaH 1 IIM-2610 and ClaH 2 Cmponenta Reactor VKHl Cla1111 1 Piping Clasa 1 Safety Injection Pipi119 ClaH 1 Residual Heat Raoval IWA-2610 1-J l*P l*P Claaa 3 I..U-5223 Circulating and Service Water TABLE I

SUMMARY

OF RELIEF REQUESTS Weld reference *vat*

..... rad llethad Weld reference

  • Y*t* per Paragraph IWA-2610 Weld reference *vat* for Reactor Weld reference Ve***l and Veaael Nozzle Ar**
  • vatea per Paragraph IWA-2610 1-J Weld aelection criteria Table IW-2500-1 Category l*J Notn 115.51 SI plpil"III between the following check valve* in the aafety injection *vat*:

1-Sl-79 AND 1*51-235, 1-Sl-241 1*S1*82 All> 1-Sl-236, 1-Sl-242 1*S1*85 AND 1*S1*237, 1*Sl*243 1*S1*88 ANO 1-Sl-238 1*S1*91 AND 1*S1*239 1*S1*94 AND 1-Sl-240 115.51 RHR plpil"III between NOV-1700 and NOV-1701 Piping upatre.. of the flrat iaolation valve in the Cl*** 3 Circulating and Service Mater

  • vat-svat* hydroatatlc tnt In accordance Mith IW-5222 Svat* hydroatatic teat In accordance Mith ua-5222 Syat* hydroatatic teat In accordance Mith I..U-5223 Page 2 of 4 Lt_... P~

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Eatlbllah... ld refar111ee Granted M/

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      • lned To uae the reference ntlbllahed by tha aut.-ted tool 251, Including ell typical hillh atrna ar...

svat* prnaure tnt c~ted Mith prnaure 100 paig lNa than the RCS noral operating preuur*

Authorized Authorized Wt thdrawn by licenaee Syat* pruaure tnt at Granted the prnaur* required by tha adjoining Claaa 2

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svat* flow tnt u allowed for open anded portions of diacharge llnu (I..U-5223(d))

Authorized

SURRY POWER STATION, UNIT 1 Page 3 of 4 Third 10-Year ISi Interval TABLE 1

SUMMARY

OF RELIEF REQUESTS

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RR 4 Class 3 lll>-52Z3 Syst.. Nvdf'ostatlc Withdrawn In COllpOMnt THt IHpDnH to Cool Ing the 9/12/94 Water

Syst.. hydrostatic Syst.. hvdf'ostatlc tnt Authorized Service piping used In the cool Ing of teat in accordance using 60 pelg u this Water cmponent cooling water for the with 111>*5Z23 ayst-PD value charging pu11p9 and llbe oil for the charging puapa RR 6 Claaa 3 lll>-5223 Auxiliary Feedwater ayst..

Syst.. hydroatatic Syst.. functional tHt Granted Aux I l iary batWNf'I th* fol lowing valvn:

tHt In accordance JIM 111>*5Z2Z Feedwater 1-FW-145 1

  • FW* 149 with 111>*5Z23 1
  • FW* 146 1-FW-609 1 *FW-160 1-FW* 163 1-FW-161 1-FW-608 1-FW-175 1-FW-179 1-FW-176 1-FW-607 RR 7 Claas 3 D-A D1.10 Circulating and Servlca Yater Systea hydrostatic Syst.. lnaervlce tut, Granted Circulating piping between valves:

tut in accordance Ul)-5221 ba perforaad In and Service 1-SW-499 1-SW-311/

with lll>-52Z3 conjunction with a Water and 1-SW-321/

visual CVT-2)

Syst-2-SW-476 2-SW-331

.... tnatlon 1-SW-317/

1-SW-346 1-SU-327/

and 2-SW-))7 2-SW-344

SURRY POWER STATION, UNIT 1 Third 10-Year ISi Interval TABLE 1

SUMMARY

OF RELIEF REQUESTS RR 8 RR 9 RR 10 RR 11 SH-1

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Cl1111s 3 Circulating and Service Water Sy11tea Repair or Replaceaent

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D*A Bolted UM-5250 Comectiona Insulated IWA-5252 lotted Comectiona COllpllWlt Support*

F*A F*I F*C D1.10 Cl*** 3 Clrculatil"IIII and Service Water Syat.. valves:

F1.10 Thru F].50 1*SW*NOV*102A 1-SW-37 and 1-SW-33 1-SW*NDV-1021 1-SW-29 1-SW-25 Corrective aeaauraaenta for leakage at boltad comectiona fcu,d during prnaure tnt Insulated bolted connectionlil Cmponent Supportll Syat* hydrostatic test In accordance with IID-5223 Syat* Hydroatatlc Tnt IIM*5250(a)(2)

IIM*5242(a)

VT-3 Vlaual Page 4 of 4 1.1....-,,....

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Syat* lrwervlce tnt, IID-5221 perforad In conj1a1etlon with a vlaual CVT-2) ex*lnatlon Granted Withdrawn in aalttal dated 6/22/94 1992 Edition of A5'1E Authorized w/

Section XI, conditions IIM*5250(a)(2) lnapac:t during outage Granted with Insulation& raoved and nan prnaurlzed Coda Cue 11-491 llot req.Jired

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