ML20078R850
| ML20078R850 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/16/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078R849 | List: |
| References | |
| NUDOCS 9412270304 | |
| Download: ML20078R850 (3) | |
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k UNITED STATE 8 g-NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2000H001
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f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l
RELATED TO AMENDMENT NO. 219 TO FACILITY OPERATING LICENSE NO. DPR-59 i
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT f
f DOCKET NO. 50-333 i
1.0 INTRODUCTION
By letter dated October 7, 1994, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A. FitzPatrick Nuclear Power Plant Technical Specifications (TSs). The requested changes would revise TS 4.6E.4 and the associated Bases to establish that the manual;'
cycling of reactor coolant system safety / relief valves (SRVs) during plant startups is to be accomplished within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after steam pressure and flow are adequate to perform the testing. TS 4.6E.4 currently requires that this testing te performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of continuous power operation at a
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reactor steam done pressure of at least 940 psig. The amendment would also make severa' editorial changes to clarify the intent of certain TSs involving SRV testing and performance requirements.
2.0 EVALUATI0d 2.1 Change to TS 4.6E.4 and Associated Bases Section TS 4.6E.4 requires that at least once each operating cycle each SRV must be manually opened while bypassing steam to the main condenser and observing at least a 10 percent closure of the turbine bypass valves. This testing must be performed within the first 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of continuous power operation at a reactor steam done pressure of at least 940 psig. The licensee has proposed that TS 4.6E.4 be modified to require the testing to be performed within the first 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after steam pressure and flow are adequate to perform the test.
The purpose of TS 4.6E.4 is to demonstrate that the SRVs are functional and that no blockage is present in the valve discharge piping. The testing is performed on the 11 SRVs during the early stages of power ascension, with reactor power less than 25 percent and at a steaming rate which can be accommodated by the turbine bypass valves.
Steaming rate is an important parameter for maintaining reactor pressure control during this testing, and testing cannot be performed until the required steam flow conditions are achieved.
9412270304 931216 PDR ADOCK 05000333 P
'TS 4.6E.4 currently requires that the manual opening of the SRVs start within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of achieving a reactor steam done pressure of.940 psig. However, as previously discussed, the testing cannot actually be performed until the-required steam flow conditions are also achieved. A period of time is required after. pressure reaches 940 psig to establish adequate steam flow, i
Part of the allotted 12-hour period to perform testing is, thus, expended to establish the appropriate. test conditions before manual opening of the SRVs can actually begin. The proposed change to TS 4.6E.4 would alleviate unnecessary stress and time )ressure on the reactor operators during reactor startu>s by allowing the 12-iour clock for manual opening of the SRVs to start when t1e required test conditions have actually been established. The proposed revision to TS 4.6E.4 would involve no change in the test method or conditions under which the SRV testing may be performed.
The staff has reviewed the proposed change to TS 4.6E.4 and concluded that it is acceptable since it will provide for manual opening of the SRVs during j
reactor startups within a reasonable time period (i.e.,12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) after the 2
appropriate test conditions have been established and alleviate unnecessary time pressures on reactor operators during reactor startups. The licensee also proposed accompanying changes to Bases Section 3/4.6E. The staff has no objections to these proposed changes to the TS Bases.
2.2 Editorial Changes to TS 4.6E.1 The licensee has proposed certain editorial changes to TS 4.6E.1.
The proposed editorial changes are described below.
A.
In TS 4.6E.1 the phrase "the 11 safety / relief valves actuate at 1110 psig 3%" would be replaced with "each valve actuates at 1110 psig 13%." TS 4.6E.1 describes the surveillance requirement for demonstrating the lift setpoint of the SRVs. Approximately half of the 11 SRVs are tested each operating cycle. The current wording in TS 4.6E.1 could be misinterpreted to require that the lift setpoint must be demonstrated for all 11 SRVs each operating cycle. The proposed change would make it clear that the lift setpoint can only be demonstrated for those valves that are tested that cycle.
B.
A new sentence would be added to TS 4.6E.1 that would read as follows:
Following testing, lift settings shall be set at 1110 psig 1%.
This proposed change would more clearly establish that the acceptance criterion for the as-found SRV lift setpoint is different from that for the as-installed setpoint.
The staff has reviewed the proposed editorial changes to TS 4.6E.1 and determined that they are administrative in nature and are, therefore, I
acceptable.
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1 2.3 Editorial Changes to Bases Section 3/4.6E The licensee has proposed several editorial changes to Bases Section 3/4.6E to clarify the intent of certain SRV testing and to eliminate the reference to two spring safety valves which are no longer installed at the facility. The staff has no objections to these proposed Bases changes.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Comission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public coment on such finding (59 FR 55889). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
5.0 CONCLUSION
The Comission has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Comission's regulations, and (3) the issuance of the amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Principal Contributor:
J. Menning Date:
December 16, 1994
_S' DATED:
December 16. 1994 AMENDMENT NO. 219 TO FACILITY OPERATING LICENSE NO. DPR-59-FITZPATRICK I
' Docket File" PUBLIC PDI-1 Reading-S. Varga, 14/E/4 J.-Zwolinski,14/H/l M. Case C..Vogan N. Conicella OGC D. Hagan, 3302 MNBB G. Hill (2), P1-22 C. Grimes, 11/F/23 ACRS (10)
OPA OC/LFDCB PD plant-specific file C. Cowgill, Region I R. Jones cc:
Plant Service list
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