ML20079H755
| ML20079H755 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/30/1991 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | FLORIDA POWER CORP. |
| Shared Package | |
| ML20079H750 | List: |
| References | |
| NUDOCS 9110140067 | |
| Download: ML20079H755 (5) | |
Text
(.
o 7590-01 UNITED Si 0F AMERICA flVCLEAR REGULATORY C0!iltlSS10N in the Matter of
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FLORIDA F0WER CORPORATICA
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Dodet No. 50-302 (Crystal River Unit 3 Nuclear GeneratingPlant)
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EXEttPTI0t!
I.
The Florida Power Corporation, et al. (FPC, the licensee) is the holder of Facility Operating License No. DPR-72, which authorizes operation of Crystal River Unit 3 Nuclear Genersting Plant (CR-3, the facility) at a steady state reactor power level not 16. excess of 2544 megawatts thermal. The license progides, among other things, that it is subject to all rules, regulations, and Orders of the fluclear Regulatory Comission (the Comission) now or hereafter in effect.
The facility is a pressurized water reactor (PWR) located at the licensee's site in Citrus County, Florida.
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II.
10 CFR Part 50, Appendix J, Section III.D 2(a) states that " Type B 4
tests, except tests for air locks, shall be performed during reactor shutdown for refueling.... but in no case at intervals greater than 2 years."
10 CFR Part 50, Appendix J, Section III.D.3 states that " Type C tests shall be performed during each reactor shutdown for refueling but in no case at intervals greater than 2 years."
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. For those containment penetrations and containment isolation valves which are the subject of this exemption, these tests would become due at CR-3 between March 1992 and May 1992. The tests necessary to meet the above-stated sections of Appendix J to 10 CFR Part 50 are also required by Technical Specification (TS)4.6.1.2(d).
By letter dated January 31, 1991, as supplemented May 16, 1991, the licensee submitted a request for a one-time exemption from Sections Ill.D.2(a) and III.D.3 of Appendix J to 10 CFR Part 50 for CR-3 for 114 inboard and outboard containment isolation valves (CIVs) and their associated containment penetrations, and electrical penetrations. The licensee proposes to perform Type B and C local leak rate tests (LLRTs) at both the containment penetrations and the CIVs prior to star *up from the eighth refueling outage (Refuel 8) for CR-S, currently scheduled to begin April 30, 1992. This would represent an extension of approximately 2 months beyond the P-year requirement of Appendix J for this fuel cycle only.
By separate correspondence dated June 20, 1991, the licensee also submitted a related TS change request which would revise TS 4.6.1.2(d) to be consistent with the requested exemption.
The licensee also responded to the Commission's staff requests for additional information related to the exemption by letter dated May 16,, 1991.
III.
As discussed in the Safety Evaluatio1 issued u th this exemption, the Comission's staff has concluded, based on the short extension requested, the satisfactory previous leak rate test results, and the small likelihood of significant degradation of components involved during the extension period, that the proposed change presents no undue risk to public health and safety.
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3 This caseLinvolves-special_ circumstances as set forth in 10 CFR 50.12(a)(2)(ii). The underlying purpose of Appendix.1, Section ll!.0.2(a)_
and !!!.D.3 is to assure leak-tight integrity of containment isolation valves and penetrations through verification of acceptable leakage by test and identification of the need for maintenance and repairs. The satisfactory history of. such tests at CR-3, the short extension of the requirad test interval, and the small likelihood that significant degradation of components will occur during the short extension, indicate that strict conformance to the 2-year testing interval requirements cf the above sections of Appendix J is not necessary to achieve the underlying purpose of these rules.
IV.
Based on the above, and on the_ review of the licensee's submittals as summarized in the Safety Evaluation issued with this exemption, the NRC staff
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concludes that the proposed exemption from certain requirements of 10 CFR Part 50, Appendix J, Section III.D.2(a) and III.D.3 presents no undue risk to public health and safety, and is acceptable.
Accordingly. the-Commission has determined that, pursuant to 10 CFR 50.12(a), the requested exemption is_ authorized by law, will not present an undue risk to-the public health and safety, and is consistent with the connon defense and security. Further, the Commission finds that special circumstances, as described'in 10 CFR 50.12(a)(2)(ii), are present in-that application of the regulation in these circumstances is not necessary:to achieve the underlying purpose of the rule.
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Therefore, the Commission hereby approves the following exemption from the requirements of Sections III.D.2(a) and II.D.3 of Appendix J to 10 CFR Part 50:
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. A temporary exemption is granted from the Type B and C testing within 2-year intervals required by 10 CFR Part 50',' Appendix J, Sections Ill.D.2(a) and 111.0.3 for the app icaole valves and penetrations on : one-time basis, provided that Type B and C tests are performed prior to startup from Refuel 8.
This exeruption shall expire prior to restart from Refuel 8, currently scheduled for June 25, 1992.
Pursuant to 10 CTR 51.32, the Comission has determined that the granting of this exernption will have no significant inpact on the environment ( 56 FR 4949).
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COMMIS$10N 1
A i
r Di e9 or Division of Reactor Pt jects - I/II Office of Nuclear Reactor Regulation Dated at Rockville, Maryland, this 30th day of September 1991.
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4-A temporary exemption is granted from the Type B and C testing within 2-year intervals required by 10 CFR Part 50, Appendix J Sections Ill.D.2(a) and III.D.3 for the applicable valves and penetrations on a one-time basis, provided that Type 9 ard C tests are performed prior to startup fron Refuel 8.
This exemption shall expire prior to restart from Refuel 6, currently scheduled for June 25, 1992.
Pursuant to 10 CFR 51.32, the Conmission has determined that the granting of this exemption will have no significant impact on the environment (56 FR 49491).
This exemption is effective upon issuance.
FOR THE NUCLEAR REGULATORY COvJilSS10N (Original Signed By)
Steven A. Varga, Director Division of Reactor Projects.1/11 Office of Nuclear Reactor Regulation Dated at Rockville, Maryland, this 30th day of September 1991.
- See Previous Concurrence
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