ML18153A751
| ML18153A751 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/30/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18153A750 | List: |
| References | |
| NUDOCS 9509080274 | |
| Download: ML18153A751 (7) | |
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ENCLOSURE 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE THIRD TEN YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN, REVISION 0 AND ASSOCIATED REQUESTS FOR RELIEF
1.0 INTRODUCTION
FOR VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNIT 2 DOCKET NUMBER:
50-281 The Technical Specifications for Surry Power Station, Unit 2 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 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 IO*CFR 50.55a(g)(6)(i).
10 CFR 50.55(a)(3) 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), 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 Cbmponents," 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 lat~st edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 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 2 third IO-year inservice inspection (ISi) interval is the 1989 Edition.
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 and subject to Commission approval.
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, information shall be submitted to the Commission 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 Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not 950908027 4 -950830 PDR*
ADOCK 05000281 Q
2 endanger life, 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.
In a letter dated March 18, 1994, Virginia Electric and Power Company submitted to the NRC its Third Ten-Year Interval Inservice Inspection Program Plan, Revision 0, and associated requests for relief for the Surry Power Station, Unit 2.
Additional information was provided by the licensee in its letter dated November 28, 1994.
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 Inservice Inspection Program Plan, Revision O and associated requests for relief for the Surry Power Station, Unit 2.
Based on the information submitted, the staff adopts the contractor's co~clusions and recommendations presented in the Technical Evaluation Report attached.
No deviations from regulatory requirements or commitments were identified in the Surry Power Station, Unit 2, Third Ten-Year Interval
- Inservice Inspection Program Plant, Revision 0.
Based on the information provided by the licensee the proposed alternatives contained in Requests for Relief Nos. SR-001, SR-007, SR-008, SR-009, SR-012, RR-2, RR-3, and RR-5 will provide and acceptable level of quality and safety and are authorized pursuant to 10CFR50.55a(a)(3)(i) with provisions for SR-009, and RR-5.
The alternative.contained in SR-009 is authorized provided that at least a 10% sample of all Code Class 1, 2, and 3 integral attachments is examined and the alternative contained in RR-5 is authorized provided that one bolt, closest to the source of leakage, is removed as part of the evaluation.
Compliance with the Code requirements regarding Requests for Relief Nos. SR-005, SR-013, and RR-6 would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety and the alternatives contained in the subject requests for relief will provide a reasonable assurance of operational readiness of systems involved in the reliefs. Therefore, the licensee's proposed alternatives contained in Requests for Relief Nos. SR-005, SR-013, and RR-6 are authorized pursuant to 10CFR50.55a(a)(3)(ii) as requested.
In the case of Requests for Relief Nos. SR-002, SR-003, SR-004, SR-006, SR-010, SR-011, RR-1, and RR-4, the licensee has demonstrated that specific Code requirements are impractical and that granting relief 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 the licensee that could result if the requirements were imposed on the facility. Therefore, relief is granted for Requests for Relief Nos. SR-002, SR-003, SR-004, SR-006, SR-010, SR-011, RR-1, and RR-4 pursuant to 10CFR50.55a(g)(6)(i) as requested
3 with the exception of SR-006.
Relief is granted for Request for Relief No.
SR-006 provided that each Class 1 and 2 piping weld examined receives all of the required reference markings as the inservice examinations are performed.
SURRY POWER STATION, UNIT 2 Third*10-Year ISi Interval
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SR-001 Reactor B-F BS.10 Vessel SR-002 Steam B-0 B3.140 Generator (Primary Side)
SR-003 Pressurizer B-0 B3.120 SR-004 Recirc.
C*G C6.10 Spray and Safety Injection Pllfl)S SR-005 Ultrasonic Calibration Block SR-006 All Class 1 and Class 2 SR-007 Reactor Vessel and Vessel Nozzle Area Page I of 4 TABLE I
SUMMARY
OF RELIEF REQUESTS Nozzle-to-Safe End Butt Welds Surface and Automated 100X Authorized volunetric volunetric exam from the examination pipe 10 surface Nozzle Inside Radius Section Vohinetric Visual (VT-1)
Granted examination examination from the nozzle 10 Nozzle Inside Radius Section Volunetric Granted examination P~ Casing Welds surface examination Visual (VT-1)
Granted examination if~ is disassembled and shaft removed for maintenance Calibration block fabrication Section XI, Use existing calibration Authorized requirements Appendix 111 and blocksSection V, Article IV Weld reference system Weld reference Establish weld reference Granted w/
system per system as welds are conditions Paragraph IWA-2610 examined Weld reference system Weld reference To use the reference Authorized system per established by the Paragraph IWA-2610 automated tool
SURRY POWER STATION, UNIT 2 Third 10-Year ISi Interval Page 2 of 4 TABLE l
SUMMARY
OF RELIEF REQUESTS
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-***= ~at..t=*~~~r SR-008 SR-009 SR-010 SR-011 SR-012 SR-013 Class 1 Piping Integrally IJelded Attachments Regen Heat Exchanger Pressurizer Class 1 and 2 piping Residual Heat Removal Heat Exchangers B*J B-D B*B B*J C-F-1 C-F-2 c-c B-J IJeld selection Selection and examination of Class 1, 2, and 3 integrally welded attachments B3.150 Nozzle-to-Vessel Welds B3.160 Nozzle inner radius sections B2.11 Head-to-Shell Weld B2.12 Longitudinal Weld B9.12 Longitudinal Welds CS.12 CS.22 CS.42 CS.52 CS.62 CS.82 C3.10 Integrally welded attachments Table 1"8-2500-1 Category B-J Notes 25X, including all Authorized typical high stress areas Surface Code Case N-509, Authorized w/
"Alternate Rules for the conditions Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments,Section XI, Division 111
- Volunetric Surface examination examination Volunetric Best effort volunetric examination examination Volunetric and/or Code Case N-524 Surface examination of at least 1211 for Class 1 and at Least 2.ST for Class 2 piping welds Surface examination Visual CVT-3) examination Granted Granted Authorized Authorized
SURRY POWER STATION, UNIT 2 Third 10-Year ISi Interval TABLE I
SUMMARY
OF RELIEF REQUESTS RR 1 RR 2 RR 3 Class 1 Residual Heat Removal Class 3 Circulating and Service Water Class 3 Service Water B*P B15.51 Class 1 piping between MOV-2700 and MOV-2701 Piping upstream of the first isolation valve Class 3 Service Water System piping used in the cooling of c~nent cooling water for the charging~ and lube oil for the charging~
System hydrostatic test in accordance with IWB-5222 System hydrostatic test in accordance with IW-5223 System hydrostatic test in accordance with IW-5223 Page 3 of 4 System pressure test Granted conducted with the normal Class 2 N-498 pressure test at the pressure required by the adjoining Class 2 system System flow test as allowed in the requirements applied to open ended portions of discharge lines (IW-5223(d))
System hydrostatic test using 60 psig as this systems PO value Authorized Authorized
SURRY POWER STATION, UNIT 2 Third 10-Year ISi Interval RR 4 RR 5 RR 6 Class 3 Auxiliary Feedwater Bolted
. Connections Insulated Bolted Connections TABLE 1
SUMMARY
OF RELIEF REQUESTS Class 3 portions of the Auxiliary Feedwater system between the following valves:
2-FW-145 2-FW-149 2-FW-160 2-FW-175 2-FW-146 2-FW-629 2-FW-164 2-FW-1l>1 2-FW-628 2-FW-179 2-FW-176 2-FW-627 Corrective actions for leakage at bolted connections found during pressure test Insulated bolted connections System hydrostatic test in accordance with IW-5223 IWA-5250(a)(2)
IWA*5242(a)
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System fll'lCtional test IWD-5222 1992 Edition of ASME Section XI, IWA-5250(a)(2)
Inspected during outage with insulation removed and no pressure requirements Granted Authorized w/
conditions Authorized
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