ML20083E905
| ML20083E905 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/27/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20083E906 | List: |
| References | |
| NUDOCS 9110030250 | |
| Download: ML20083E905 (2) | |
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SAFETY EVALUAT10t' BY THE OFFICE OF NUCLEAR REACTOR RFGULATION RELATED TO THE INSERVICE TESTING PROGRAM RELIEF RE0 HEST FLORIDA POWER CORPORATION CRYSTAL RIVER, !! NIT 3 DOCKET !!0. 50-302
1.0 INTRODUCTION
i The Code of Federal Regulations, 10 CFR 50.55a(g), requires that inservice testing (IST) of certain ASf1E Code Class 1, 2, and 3 valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (Code) and applicable adoenda, except where specific written rellef has been requested by the licensee and granted by the Comission pursuant to Subsections (a)(3)(1),
(a)(3)(ii), or (g)(6)(1) of 10 CFR 50.553 These regulations authorize the Comission to grant relief from ASME Code requirements upon making the necessary findings.
By letter dated January 31, 1991, as supplemented May 16, 1991 Florida Power Corporation (the licensee) requested a one-time exemption from the surveillance freqJency requirements of 10 CFR part 50, Appendix J, and relief from the related requirements of ASME Code, Section X1, and 10 CFR 50.55a.
The exemption from Appendix J is evaluated under separate cover. The NRC staff's findings with respect to the relief requested as part of the licensee's IST program are contained in this $afety Evaluation (SE).
2.0 EE*CR1pTION AND DISCUSSION in response to NRC Generic Letter (GL) 89-04 " Guidance on Developing Acceptable inservice Testing Programs," Position W " Containment isolation Valve Testing,"
the licensee indicated their intention to leak test containment isolation valves (CIVs) per the requirements of 10 CFR Part 50, Appendix J, to comply with ASME Code,Section XI, 1WV-3421 through IWV-3425.
Appendix J requires Type C testing of containment isolation valves during refueling outages but in no case at intervals greater than 2 years.
Code paragraph IWV-3422, " Frequency,"
requires that valve leak rate tests be conducted at least once every 2 years.
Refueling outage 8 (Refuel 8) is scheduled to begin April 30, 1992.
Valve leakage testing is presently required to be completed on a number of valves between March 1992 and May 1992. To accomplish the required testing within the 2-year interval would require an otherwise unnecessary shutdown. Delaying the testing until Refuel 8 would result in an approximately 2-month extension of i
the 2-year test interval.
l 9110030250 910927 POR ADOCK 05000302 P
f'DR
2 2.1 Relief Request V-374 The licensee has requested relief frem the test frequency requirements of 1WV-3422 for a one-tine extension of the leakate rate test interval from once every ? years to an interval from the last test until the end of Refuel B.
The relief request is applicable to containment isolatica valves and feedwater isolation valves as listed in the enclosure to the licensee's letter of May 16, 1991, 2.2 Alternative Testing The licensee has proposed to complete the required leakage testing during Refuel 8 scheduled to start April 30, 1992.
The testing will meet the requirements of 10 CFR Part 50, Appendix J, and ASME Section 11, 1WV-3426 and 1WV-3427(a), in accordance with the Crystal Piver-3 Intervice Testinq Program.
2.3 Licensee's Jasis for relief The licensee states in their January 31, 1991, letter:
1.
The CR-3 Pump and Valve Program utilizes 10 CFR Part 50, Appendix J. Local t.eak Rate Testing to fulfill the requirements of ASME Section XI,1WV-34?2.
The intent of Appendix J is t > a' low Type "C" testing (containment isolation valves) to be performed during refuelina outages.
CR-3 is requesting a one-time extension of the test interval to cointide with the rext scheduled refueling outage.
2.
The condition of the components is not expected to change during the requested extension period.
This extension period is relatively short in comparison with the 2-year test interval.
3.
The Type "C" testing performed during Refuel 7 (1990) provided favorable results with the measured leakaae (approximately 10% of allowable leakage).
4 T ht. integrity of the isolation valves' leak tightness will be verified by a Type "A" test (Integrated Leak Rate) scheduled for October 1991.
3.0 EVALUATION AND CONCLUSION Based on the short extension requested, the low likelihood of a significant change in the condition of the components involved during the extension period, and the history of acceptable leak rate testing in the past, we conclude that leak rate testing of the valves in question during Refuel 8 would provide an acceptable level cf quality and safety, and is acceptable. Therefore, the requested relief may be granted pursuant to 10 CFR 50.55a(a)(3)(i).
Principal Contributors:
P. Campbell H. Silver Date: September 27, 1991 o
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