ML17059A972
| ML17059A972 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/16/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059A971 | List: |
| References | |
| NUDOCS 9510230029 | |
| Download: ML17059A972 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20RI5-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
155 TO FACILITY OPERATING ICENSE NO.
DPR-63 G
RA MOH WK POW R
CORPO 0
NI E
M POINT NUCLE S ATION U NO 1
DOCKET NO. 50- 20
- 1. 0 INTRODUCTION By letter dated February 1,
- 1995, Niagara Mohawk Power Corporation (the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station Unit No.
1 (NHP1), Technical Specifications (TSs).
The proposed changes alter the requirements for the Limiting Conditions for Operation and-the Bases for the instrumentation and controls for the remote shutdown capability at NHP1.
The licensee proposes these changes to bring consistency between the NMPl TSs and NUREG-1433, "Standard Technical Specifications General Electric Boiling Water Reactors (BWR/4)."
The licensee's submittal includes the justification for the proposed changes and provides the basis for the no significant hazards consideration.
2.0 BACKGROUND
The remote shutdown panels provide 1) manual initiation of the emergency condensers
- 2) manual control of the steam supply valves and 3) parameters monitoring independent of the main/auxiliary control room.
Two panels are provided; each located in a separate fire area for added redundancy.
Both panels are also in separate fire areas from the main/auxiliary control room.
One channel of each Function provides the necessary capabilities consistent with 10CFR50 Appendix R.
Therefore, only one channel of either remote shutdown panel monitoring instrument or control is required to be operable.
The electrical design of the panels is such that no single fire can cause loss of both emergency condensers.
The existing TS requires that at least one remote shutdown panel be operable during power operation and when the reactor coolant temperature is above 212 F.
When this requirement cannot be met, an orderly plant shutdown must commence within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and cold shutdown must be reached within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
A remote shutdown panel is considered inoperable if any of the presently-required control or instrumentation functions is not operable in that panel.
These required functions include the emergency condenser return valve control switch, either of the motor-operated steam supply valve control switches, and the required operable instrument channels as indicated in Table 3.6.13-1, "REMOTE SHUTDOWN PANEL MONITORING Limiting Condition for Operation."
9510230029 9510lb PDR ADOCK 05000220 P
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The licensee indicated that the existing TS requirements are overly conservative compared to NUREG-1433 and to Amendment No. 216 issued to the James A. FitzPatrick Nuclear Power Plant on August 31,
- 1994, and has proposed changes to relax the existing requirements and thereby preclude unnecessary plant shutdowns.
3.0
~VA UATION The proposed changes relax the existing requirement that all of the required functions must be operable on the same remote shutdown panel, and require instead that between the two remote shutdown panels, one channel of each required function be operable.
The operators communicate with one another and the remaining personnel from each panel using the plant Gaitronix system.
These changes could potentially avoid an unnecessary plant shutdown without affecting an operator's ability to cope with a control room evacuation.
One channel of each function is adequate to assure a safe shutdown.
The NRC staff finds the above to be consistent with NUREG-1433 and is, therefore, acceptable.
The proposed TS changes also allow 30 days to restore an inoperable function
'o operable status.
If this action is not completed, then the plant must be-brought to a hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The staff finds that this is consistent with NUREG-1433 and is, therefore, acceptable.
With one or more of the required monitoring instrument functions inoperable, the TS changes propose to allow the licensee an additional option.
Specifically, the operator is allowed 30 days to establish an alternate method of monitoring the parameter and 90 days to restore the function to operable status.
The staff finds that at NHPl the temporary provision of an alter nate method for monitoring the required instrumentation function, located remote from the control zone and consistent with Appendix R, is consistent with the intent of NUREG-1433 because it will provide the operator with indication of the parameter of interest, and is acceptable.
The proposed TS changes remove Hode 3 (Hot Shutdown) from the existing specification for operability by deleting the phrase "whenever the reactor coolant temperature is greater than 212 'F" from the existing specification.
The staff finds that this change, removal of Hode 3 from the requirement for operability, is consistent with NUREG-1433 which requires operability only during Hode 1 (Power Operation) and Hode 2 (Startup/Hot Standby) and is, therefore, acceptable.
The proposed TS changes require that the plant be bought to a hot shutdown condition in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (versus a cold shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />).
As indicated in NUREG-1433, the 12-hour completion time is reasonable based on operating experience.
The staff finds that this change is consistent with NUREG-1433 and is, therefore, acceptable.
>> ~
The licensee proposes to revise Bases Sections 3.6. 13 and 4.6. 13 to provide consistency with the proposed changes to the TSs.
The Bases Section currently indicates that one remote shutdown panel is required to be operable.
In the proposed TS change, one channel of each function (between the two panels) is required to maintain remote shutdown operability.
The staff finds that the revisions to the Bases Section are consistent with NUREG-1433 and are, therefore, acceptable.
Editorial changes are made to Table 3.6. 13-1 for consistency with the proposed changes to the TSs.
Specifically, the word "INSTRUMENT" is changed to "FUNCTION" and the words "PANEL MONITORING" are changed to the words "PANELS FUNCTIONS."
These changes make clear the proposal that one operable channel of each function (between the two panels) is acceptable to maintain operability.
The operability requirements for the emergency condenser condensate return valve control and motor-operated steam supply valves control are relocated from Specification 3.6. 13.b to Table 3.6.13-1 for consistency with the proposed changes.
The staff finds that these editorial changes are consistent with NUREG-1433 and are, therefore, acceptable.
Based on the review of the licensee's submittal, the staff concludes that the;:
proposed TS changes are consistent with NUREG-1433 and previously approved TS.
changes and are, therefore, acceptable.
4.0 STA E CONSULTATIO 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.
- 5. 0 ENVIRONMENTAL CONSIDERATION The amendment changes a requirement'ith respect to installation or use of a 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 significant increase in individual or c'umulative 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 (60 FR 11135).
Accordingly, the amendment meets the eligibilitycriteria 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.
4
6.0
~CONCLUS 0 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:
K. Hortensen pate.
October 16, 1995
C c'
'P DATED:
October 16, 1995
)I AMENDMENT NO.
155 TO FACILITY OPERATING LICENSE NO. DPR-63-NINE MILE POINT UNIT NO.
1
%Docket F.i,le" PUBLIC PDI-1 Reading S. Varga, 14/E/4 L. Harsh S. Little G. Edison OGC K. Hortensen G. Hill (2)
C. Grimes ACRS (4)
C. Cowgill, RGN-I cc:
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