ML20028F080
| ML20028F080 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/27/1983 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20028F081 | List: |
| References | |
| JPN-83-08, JPN-83-8, NUDOCS 8301310128 | |
| Download: ML20028F080 (5) | |
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POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMBUS CIRCLE New YORK, N. Y.10019 42123 397.6200 LEnov . Lain 1.u.v... ................
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MICH ARD M. PLYNN a ssea.n a m ROBE RT 1. MILLoN ZI 1EPHE 65
. , , o ,, y,C e a .ees se, er esseen A6 covesses Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Proposed Change to the Technical Specifications Related to Single-Loop Operation
Reference:
Letter J. P. Bayne (PASNY) to T. A. Ippolito (USNRC) dated December 29, 1982; Proposed Change to the Technical Specifications Related to Single-Loop Operation (JPN-82-92)
Dear Sir:
The Authority submitted a proposed amendment to the James A. FitzPatrick Nuclear Power Plant Operating License via the reference letter. This change would allow the plant to be operated at reduced power with one recirculation loop out of service.
Inadvertently, this proposed amendment was transmitted to you without the appropriate copies of the associated safety evaluation (Attachment II) or the General Electric Report entitled "FitzPatrick Nuclear Power Plant Single Loop Operation," NEDO-24281. Enclosed with this letter are forty copies of the safety evaluation and the General Electric report to complete the amendment application.
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8301310128 830127 PDR ADOCK 05000333 P PDR
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If you have any questions about these submittals, please contact Mr. J. A. Gray, Jr. of my staff.
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Very truly yours, '
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- J. P. Bayne Executive Vice President Nuclear Generation l
Enclosure cc: fir. J. Linville l Resident Inspector l U. S. Nuclear Regulatory Commission
' P. O. Box 136 Lycoming, NY 13093 i
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4 ATTACl! MENT II ,
SAFETY EVALUATION RELATED TO SINGLE RECIRCULATION LOOP OPERATION POWER AUT!!ORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
4 Section I - Description of_the Changes The proposed amendment allows operation of the reactor with one recirculation loop out of service at reduced power. Adjustments are made to the flow biased APRM Scram .rul Rod Block lines, as well as the flow biased Fod Block Monitor line, to account for the change in core flow versus recirculatice flow behavior during single-loop operation. The MCPR fuel cladding integrity safety limit is raised by 0.01 during single-loop operation for increased uncertainties in total core flow and TIP reading. A reduction factor is applied to each MAPLHGR curve to account for the difference in LOCA analysis of
.cne loop versus two-loop operation. The largest contribution to a decrease in MAPLHGR for one-loop operaticn is the very short time to onset of boiling transition used, 0.1 sec versus approximately 10 see in the two-loop analysis. This conservative assumption is a result of the decrease in forced circulation provided by recirculation pump coast down during the early stages of a LOCA.
A description of analyses referred to in this section can be found in General Electric report NEDO-24281 (as amended) entitled, "FitzPatrick Nuclear Power Plant Single-Loop Opeation". Copies of this report are included in the submittal to the NRC.
Surveillance testing of the operating recirculation loop will include verification of jet pump operability by monitoring jet pump instruments, and comparing the readings with baseline readings.
These baseline readings are taken each time single loop recirculation is initiated.
Section II - Purpose of the Changes The current Technical Specifications for FitzPatrick do not allow plant operation for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with one recirculation loop out of service. However, the capability of operating at reduced power with a single recirculation loop is highly desirable from a plant availability standpoint in the event maintenance on a recirculation pump or other component renders one loop inoperative.
Section III - Impact of the Changes The changes to the Technical Specifications outlined in Section I of this evaluation ensure that the consequences of plant transients and accidents analyzed in the FSAR are unaffected during the single-loop operation, and do not alter conclusions reached in the FSAR and SER accident analysis.
The reduced power in single-loop operations ensures that pressurization transients are less severe as seen in Figure 3-1 of NEDO-24281. MAPLHGR reduction factors account for the decrease in blowdown heat transfer during a LOCA and maintain the fuel within the 2200*F peak clad temperature limit required by Appendix K of 10 CFR 50.
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'Section IV - Implementation of the Changen
> These changes, as proposed, will not impact the ALARA or Fire Protection Programs at JAF. These changes will not impact the environment.
Section V - Conclusion i
The incorporation of these changes: 'a) will not increase the probability nor the consequences of an accident or malfunctivn of equipment important to safety as previously evaluated in the Safety .
Analysis Report; b) will not increase the possibility for an i accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report; and c) will not reduce the margin of safety as defined in the basis for any Technical
. Specification, and d) does not constitute an unreviewed safety j question.
Section VI - Reference (a) JAF FSAR (b) JAF SER (c) General Electric Company Report NEDO-24281, "FitzPatrick Nuclear Power Plant Single-Loop Operation" .
(d) General Electric Company Service Information Letter (SIL)
No. 330, " Jet Pump Beam Cracks", June 9, 1980.
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