ML20065H433
| ML20065H433 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/06/1994 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065H430 | List: |
| References | |
| NUDOCS 9404150003 | |
| Download: ML20065H433 (4) | |
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4 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 209 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated December 28, 1993, 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 clarify Limiting Condition for Operation (LCO) 3.5.D.4.
Specifically, Amendment No.179 to the TS added LCO 3.5.D.4 to permit hydrostatic and leakage testing at temperatures up to 300 *F without
[i requiring certain equipment, including the automatic depressurization system (ADS), to be operable. However, LC0 3.5.D.4 can be mistakenly interpreted to require the ADS be operable at temperatures less than 212 'F.
Requiring the ADS to be operable during hydrostatic and leakage testing with temperatures below 212 'F was clearly not the intent of Amendment No.179. The amendment would clarify LCO 3.5.D.4 to resolve this concern and is considered an administrative change.
2.0 EVALUATION As outlined in Chapter 6 of the Updated Final Safety Analysis Report (UFSAR),
" Emergency Core Cooling System (ECCS)," in the event of a Loss-of-Coolant Accident (LOCA), the ECCS is designed to remove residual heat including stored heat and heat generated due to radioactive decay, such that excessive fuel clad temperature is prevented. The objective of the ECCS is to limit, in conjunction with primary and secondary containments, the release of radioactive materials to the environs following a LOCA so that resulting radiation exposures are kept within the guideline values given in 10 CFR Part 100.
Four systems are provided for emergency core cooling:
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High-pressure Coolant Injection (HPCI) System 2.
ADS System 3.
Core Spray System 4.
Low-pressure Safety Injection (LPCI), an operating mode of the RHR System l
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The Automatic Depressurization System is provided to automatically reduce reactor coolant system pressure if a break has occurred and vessel water level is not maintained by the HPCI systein and other high pressure water addition systems. Rapid depressurization of the reactor coolant system is desirable to permit flow from the Core Spray and LPCI systems to enter the vessel, so that the temperature rise in the core is limited.
On March 9, 1992, the NRC staff issued Amendment No. 179 to the FitzPatrick Technical Specifications. The purpose of this amendment was to allow hydrostatic pressure and leakage testing of the reactor coolant system boundary at temperatures up to 300 *F without requiring certain safety related systems, including ADS, to be operable. However, LCO 3.5.D.4, as approved by Amendment No. 179_could be misinterpreted as requiring ADS to be operable
'during hydrostatic pressure and leakage testing below 212 *F while exempting the operability requirement between 212 'F and 300 *F.
The proposed clarification of LC0 3.5.D.4.to allow hydrostatic pressure and leakage testing below 300 *F without requiring the ADS to be operable corrects the specification to read as originally intended by the associated NRC Safety _
Evaluation (SE).
The NRC staff has reviewed the licensee's proposed amendment and has
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determined that the change is administrative in nature.. The SE prepared by 1 the NRC staff to support TS Amendment No. 179 found that hydrostatic pressure and leakage testing of the reactor coolant system boundary at temperatures up to 300 *F, without requiring ADS to be operable, had no adverse impact on plant safety and was acceptable.
The change made to LC0 3.5.D.4'in the proposed amendment only clarifies the specification to read as originally intended and does not affect the conclusions of the NRC staff safety evaluation prepared for TS Amendment No.179.
In summary, the change is determined to be administrative in nature and is approved.
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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 l
l facility component located within the restricted area as defined in 10 CFR Part 20. 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 j
significant increase in individual or cumulative occupational radiation _
l exposure. The Commission has previously issued a proposed finding that the.
amendment involves no significant hazards consideration, and there has been no l
public comment on such finding (59 FR-10014). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR O
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, 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 Commission 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 Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Brian C. McCabe Date: April 6,1994 J
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Docket No. 50-333 April 6, 1994 Mr. William A. Josiger, Acting Executive Vice President - Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601
Dear Mr. Josiger:
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC NO. M88537)
The Commission has issued the enclosed Amendment No. 209 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendment consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated December 28, 1993.
i The amendment clarifies Limiting Condition for Operation (LCO) 3.5.D.4.
Amendment No. 179 to the TS added LC0 3.5.D.4 to permit hydrostatic and leakage testing at temperatures up to 300 *F without requiring certain equipment, including the automatic depressurization system (ADS), to be.
operable. However, LC0 3.5.D.4 can be mistakenly interpreted to require the ADS be operable at temperatures less than 212
- F.
Requiring the ADS to be operable during hydrostatic and leakage testing with temperatures below 212 *F was clearly not the intent of Amendment No. 179. The amendment clarifies LC0 3.5.D.4 to resolve this concern and is considered an administrative change.
A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in the Commission's next regular biweekly Federal Reaister notice.
Sincerely, Original signed by:
Brian C. McCabe, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Amendment No. 209 to DPR-59 2.
Safety Evaluation j
cc w/ enclosures:
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