ML20080G520
| ML20080G520 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/30/1995 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080G518 | List: |
| References | |
| NUDOCS 9502080128 | |
| Download: ML20080G520 (6) | |
Text
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UNITED STATES y
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,j NUCLEAR REGULATORY COMMISSION
't WASHINGTON, D.C. snans mi SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 223 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW Y0g l
JAMES A. FITZPATRICK NUCLEAR POWER PLMI DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated September 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 (TS). The requested 1
changes would revise TS Section 4.11.D to change the surveillance requirements for the Emergency Service Water System (ESWS) pumps.
Specifically, the change would add pump flow rate requirements and would test the pumps in accordance with the licensee's Inservice Testing (IST) Program. To add operational flexibility, the pump flow rate requirements would be based on changes to the system alignment, revised heat load calculations, and revised component flow calculations.
In addition, the respective TS Bases would be revised.
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2.0 EVALUATION
2.1 Background
In NRC Inspection Report No. 50-333/90-04, dated August 6, 1990, inspectors identified several weaknesses with the licensee's ESWS. One of the concerns expressed in Unresolved Item 90-02-06 of the report dealt with periodic surveillance testing of emergency service water (ESW) pumps.
On August 21, 1990, an enforcement conference was held regarding violations cited in the aforementioned report. The licensee identified certain limitations with the "!, hut off head" ESW pump surveillance test that was required by the current plant TSs. The licensee conmiitted to submit a TS change requiring an improved ESW pump test.
In a letter to the NRC, dated April 15, 1991, the licensee clarified its commitment and stated that the test requirements would reflect the appropriate sections of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) and the FitzPatrick IST Program based on revised ESWS flow requirements.
In NRC Inspection Report No. 50-333/92-81, dated June 11, 1992, inspectors identified two errors in a safety evaluation submitted by the licensee in 9502000128 950130 DR ADOCK 0500 3
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2-support of a TS change, datad November 11, 1991, to revise ASME Code Section XI and ESW pump surveillance testing. The resolution of these errors and results of actual system testing were used to support the currently proposed amendment.
2.2 Assessment The ESW system consists of two independent supply loops each with an ESW pump to provide cooling for a safe reactor shutdown.
The present Surveillance Requirement (SR) for testing of the ESW pumps specifies a minimum pump total developed head at zero flow for each ESW pump.
This is also known as a shut off head test. The proposed SR will alleviate the shortcomings of the current test by demonstrating the capability of the pumps to provide flow to the system and minimize the wear caused by shut off head testing.
The proposed SR would also decrease the minimum required flow to provide operational flexibility to deal with microbiological 1y induced corrosion (MIC) which restricts flow to the crescent area coolers. To allow for reduced flow, the licensee has revised the system line-up, taken credit for the margin in the original cooler designs and revised calculated heat loads to remove excess cor.servatism.
The proposed SR will demonstrate that the ESW pump continues to remain operable. The acceptability of the proposed test to demonstrate pump operability was determined by the licensee, based on three factors:
- 1) a j
determination of minimum ESW system flow requirements; 2) an evaluation of the system hydraulic characteristics; and 3) the licensee's IST program procedures. The results of the licensee's review of the above three areas are 1
presented below.
2.2.1 System Flow Requirements The proposed SR specifies that each pump is to be tested by delivery of flow of "at least 1500 gpm to its respective loop." The proposed SR is written so that the pump test flow requirements are above the minimum flow of the ESWS.
This assures that pump operability testing is done with flow above the minimum flow required by the system.
The minimum flow requirement to all components in the normally aligned configuration, which includes components required for design basis events, is 1400 gpa and 1438 gpm for trains A and B, respectively. The current SR calls for a 3250 gpm total flow, or approximately 1625 gpm per loop. The proposed SR calls for a reduction in flow of approximately 125 gpm per loop. This reduction in flow also reduces the heat removal capability of the system; however, according to the licensee, the system will continue to provide adequate heat retsval capacity.
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. The flow calculations, completed by the licensee, identify heat loads for design basis conditions, identify equipmer.t required to function and the required valve line-up to limit flow, r..sume degraded conditions in the unit coolers, and assume that the lake watrr for the ESW system intake is at 82 'F.
e The equipment required to function ar.d the minimum flow requirements and system alignment are presented in the table below.
Cooling Unit N:merical Train Flow Designation Required (gan)
One' t' rain of the following equipment must remain operational and the ESWS must provide the indicated minimum flow to remove heat loads.
emergency diesel generator 93WE A,B 1000 cooling jacket C,D 1000 electric bay coolers 67UC - 16 A
35 B
45 crescent area coolers 66UC - 22 A,C,E,G,J 120 B,D,F,H,K 120 cable tunnel /switchgear 67E 11 12 room coolers 14 12 control room air handling 70AHU - 3 A
110 units (AHUs)
(normally isolated)
B 110 relay room air handling 70AHU - 12 A
90 units (normally isolated)
B 90 The following equipment is non-safety related, but will remain aligned to and be supplied by ESWS following an accident.
cuntrol room chillers 70RWC - 2 A
226 B
226 chiller room air '
70RWC - 19 A
14 handling units lB 14
- 1. Bott AHUs are supplied by Train B
V i
Cooling Unit Numerical Train Flow Designation Required (gpm) control rod drive (CRD) 3P - 16 A
7 pump coolers B
7 The following equi ment is non-safety related and ESW will normally be isolated from taese systems to assure flow to required components RHR pump seal water 10E - 3 A, C No flow coolers B, D recirculation pump motor 02 - 2P - 1 A
No flow and seal B
equipment sump cooler 20E - 9 A
No w drywell coolers 68E - 1 A,B,C,D No flow 68E - 3 A,B,C,D The following equipment is normally isolated but will be opened for intermittent use during the post accident period post accident sampling SSC - LSC 1
10 system cooler The minimum flow requirement for the normally aligned configuration discussed sbove is 1400 gpm and 1438 spm for trains A and B, respectively. This flow is higher than the minimum flow required to remove heat in the worst-case accident (i.e., 1367 gpm and 1377 gpm for trains A and B, respectively) because the safety relattd control room and relay room air handling units are normally isolated from the ESWS.
As long as the nonsafety control room chillers and chiller room AHUs remain functional, they are relied upon to provide cooled glycol to the control room and relay room AHUs.
If func.tional capability is lost, the nonsafety control room chillers and chiller room AHUs would be manually isolated and ESW flow would be manually realigned to the control room and relay room AHUs. The proposed manual realignments would be executed during a post-accident scenario. This realignment is documented in the revised Bases Sections 3.11 and 4.11.D of the TSs.
Based on the above, even though the ESW system flow rate has been reduced, it will provide sufficient cooling to the required components.
The revision of
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. i the system line-up, which would occur in response to a failure of the nonsafety related control room chillers and chiller room AHUs, is sufficient to insure continued cooling to the control room and relay rooms. Therefore, the NRC staff finds that the proonsed changes in system flow rate and post-l accident system line-up to be acceptable.
2.2.2 System Hydraulics The proposed SR specifies that "The pump total developed head shall be greater than or equal to the corresponding point on the pump curve, reduced by a maximum of 7%, for the measured flow." The licensee determined by analysis using a computer model of the ESWS that 7 percent degradation of the ESW pumps will retain sufficient ESW flow to meet cooling requirements at a minimum lake 1
water level should the strainers become 75 percent fouled. Based on the above, the NP.C staff believes that ESW pump operability will be sufficiently established with a comparison to the pump performance curve, with the 7 percent margin for degradation.
2.2.3 Testing Procedures In addition to Surveillance Test (ST) 8D currently performed to meet TS SR 4.ll.D.I.b, the licensee also conducts other ESW testing. ST 80 is performed to determine and set ESW flow rates to individual safety-related components while providing flow to all of the equipment aligned during normal operation except the CRD pump coolers (this omission has a negligible effect on the test due to the small rate of flow to the CRD pump coolers). Also, STs 19C, 19G, 19H, and 191 are performed to monitor the heat removal capability of various area coolers. Finally, ST 8N is currently performed quarterly to meet IST requirements.
ST 8N will also be used to demonstrate operability of the ESW pumps under the proposed SR. This test is performed with a pump flow supplying equipment c
l aligned to the respective pump loop during normal operation of at least 1500 gpe, which exceeds the calculated minimum flow for that alignment. The licensee established by analysis that an ESW pump is operable when the total developed head measured for the pump under test exceeds 93 percent of the reference pump curve value for total developed head at the test flow rate.
ST 80, the shut-off head test, will be discontinued upon the approval of this proposed TS change.
Based on the above, the NRC staff finds that the ST 8N will be sufficient for determining ESW pump operability, and therefore will r.eet the purpose of the proposed SR.
2.3 Summary The NRC staff concludes, based on the considerations discussed above, that the proposed SR wili sufficiently determine the operability of ESW system pumps.
In addition, the calculations presented to support the reduction of ESW system i
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flow indicate that there will be sufficient cooling of the required components supplied by ESW under accident conditions. Therefore, the NRC staff finds I
that the proposed change is acceptable.
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.
l 4.0 ENVIR0l#4 ENTAL 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 ir.dividual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (58 FR 62156). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR r
51.22(b) no environmental impact statement or environmental assessment need be prepare? ln connection with the issuance of the amendment.
5.0 CONCLUSION
i 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 t:e 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:
C. Bajwa Date: Januar, 30, 1995 l
l
f-l January 30, 1995 Mr. William J. Cahill, Jr.
Executive Vice President - Muclear Generation Power Authority of the State of New York 123 Main Street White Plains, NY 10601
SUBJECT:
ISSUANCE OF AMENDMENT FOR JAMEL t..
FIT 7 PATRICK NUCLEAR POWER PLANT (TAC NO. M88088)
Dear Mr. Cahill:
The Comission has issued the enclosed Amendment No.223 to Facility Operating License No. DPR-59 for the James A. FitzPatrick Nuclear Power Plant. The amendent consists of changes to the Technical Specifications (TSs) in response to your application transmitted by letter dated September 28, 1993.
The amendment revise: TS Section 4.11.D to change the surveillance requirements for the Emergency Service Water System pumps.
The change addt pump flow rate requirements and tests the pumps in accordance with your Inservice Testing Program. To add operational flexibility, the pump flow rate requirements are based on changes to the system alignment, revised heat load calculations, and revised component flow calculations.
In addition, the respective TS Bases have been revised.
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 Nicola F. Conicella, Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office af Nuclear Reactor Regulation Docket No. 50-333
Enclosures:
1.
Amendment No. 223to DPR-59 2.
Safety Evaluation cc w/encls:
See next page j
Distribution:
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