ML20247C168
| ML20247C168 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/05/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247C160 | List: |
| References | |
| NUDOCS 8909130264 | |
| Download: ML20247C168 (2) | |
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'i UNITED STATES l 8, NUCLEAR REGULATORY COMMISSION o
h WASHING TON, D.' C. 20555 l
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I SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION l
2 l
RELATED TO AMENDMENT NO.136 TO FACILITY OPERATING LICENSE NO. DPR-59 l
POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 l
1 INTRODUCTION By "05000333/LER-1989-006-01, :on 890419,standby Liquid Control Sys Declared Inoperable When Pump Discharge Accumulator [[Atomic Element" contains a listed "[" character as part of the property label and has therefore been classified as invalid. Precharge Was 0 Psig.Caused by Slow Leak in Charging Connector Spring Loaded Valve.Bladder Repaired|letter dated May 19, 1989]], the Power Authority of the State of New York 1
(PASNY or the licensee) requested changes to the Technical Specification (TS) for the James. A. FitzPatrick Nuclear Power Plant. The changes would~ revise Tables 4.1-1, 4.1-2 and 4.2-1 to correct certain errors which were introduced' by previous TS amendments and to correct an editorial error in Table 4.1-2.
DESCRIPTION TheproposedchangetoTable4.1-1,"ReactorProtectionSystem(Scram)
Instrument Functional Test," and Table 4.1-2, " Reactor Protection System (Scram) Instrument Calibration," would remove the testing requirements associated with the reactor pressure permissive switches which establish the pressure setpoint below which the main steam itne isolation valve (MSIV) reactor scram signal and the MSIV isolation signal on low condenser vacuum i
signal are bypassed when the mode switch is in the refuel or startup l
positions. Removal of the pressure switches (designated 02-3PS-51 A through D) from the scram and the Primary Containment Isolation System (PCIS) logic requirements of TS Table 3.1-1, " Reactor Protection System (Scram)
Instrumentation Requirements," and Table 3.2-1, " Instrumentation that
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Initiates Primary Containment Isolation," was approved in Amendment No.122, 1
dated February 7, 1989. However, due to an oversight, the submittal for this amendment did not address the related instrument tests designated in Tables 4.1-1 and 4.1-2.
Since the safety analysis concerning removal of the j
switches has already been performed in Amendment No. 122, with the determination j
that there is no adverse impact on safety, removal of the testing requirements is equally justified and is approved.
l Another change to Table 4.1-2 would correct a typograp'hical error introduced in Amendment No. 89 by changing " Trip System Traverse to "TIP System Traverse."
All previous amendments which affected this table reflect use of the abbreviation "TIP" and Amendment No. 89 does not address a change to this terminology.
In addition, to perform an LPRM Signal Instrument channel Calibration, a Traversing Incore Probe (TIP) System traverse method is used, as described in the Final Safety Analysis Report. Also, the change would make the table consistent with the description in the TS Bases.
For these reasons, the change is determined to be editorial in nature and is approved.
8909130264 890905 PrtR ADOCK 05000333 P
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'The proposed change to Table 4.2-1, " Minimum Test and Calibration Frequency.
for,PCIS," would change the water level instrument designation from Low-Low to Low-Low-Low. This instrumentation causes the main steam isolation valves, the-
' main steam line drain valves,-the. reactor water sample valves, and the standby-gas treatmant system reactor building isolations valves, to shut automatically.
The actual change to the setpoint was issued as Amendment No. 103, dated December 19,'1986. However, due to an oversight, the submittal for this amendment did not address the related instrument tests designated in Table.
4.2-1. -Since the safety analysis concerning the setpoint change has already been performed in Amendment No. 103, with the determination that there is no t
adverse impact on safety, the change to the table is considered to be editorial and will result in improved TS consistency.
It is, therefore, approved.
ENVIRONMENTAL-CONUDERATICE This amendment involves a change to surveillance requirements. The 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 Connission has previously issued a proposed -
finding that this amendment involves no significant hazards consideration and-there.has been no public comment on such finding. Accordingly, this amendment meets-the eligibility criteria for categorical exclusion set forth in 10 CFR Part51.22(c)9). Pursuant to 10 CFR Part 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the
-issuance of this amendment.
CONCLUSION We have 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, and (2) such activities will be conducted in compliance with the Commission's regulations ans' the issuance of this amendment will not be. inimical to the common defense and security or to the health and safety of the public.
Dated:
September 5, 1989 PRINCIPAL CONTRIBUTOR:
D. LaBarge I