ML20128E633
| ML20128E633 | |
| Person / Time | |
|---|---|
| Site: | Brunswick |
| Issue date: | 02/03/1993 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20128E617 | List: |
| References | |
| NUDOCS 9302100529 | |
| Download: ML20128E633 (3) | |
Text
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UNITED STATES N
NUCLEAR REGULATORY COMMISSION
{
E WASHINoTON, D. C. 20555
%.....l MFllLEVALVATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 160 TO FACll!TY OPERATING LICENSE NO. DRP-71 AND AMENDMENT NO. 191 TO FACILITY OPERATING LICENSE NO. DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT. UNITS 1.AhD 2 D_Q GET NOS. 50-325 AND 50-324
1.0 INTRODUCTION
By letter dated Novemter 16, 1992, as supplemented January 25, 1993, Carolina Power & Light Company (CP&L or the licensee) submitted a request for changes to the Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick), Technical Specifications (TS). The January 25, 1993, letter provided updated TS pages and did not change the initial submittal noticed in the Federal Reaister.
The requestcd changes would allcw a one-time only revision to the requirements of Section 3.3.3 of Technical Specification 3/4.3.3, Emergency Core Cooling System Actuation Instrumentation, when in Operational Condition 4 (Cold Shutdown) to support modifications to upgrade the seismic qualification of instrument racks H21-P009 (Unit 2 only) and H21-P010 (Unit I and Unit 2).
The amendments will allow the minimum number of operable channels for one reactor steam dome pressure - low instrumentation trip system to be temporarily reduced from two (2) channels to one (1) channel.
This will allow, on three separate occasions d ring this present outage, one reactor steam dome pressure
- low (injection permissive) channel to be placed in the condition (tripped) that will satisfy the logic for allowing injection by the associated emergency core cooling system (ECCS) for op to seven (7) days without invoking the associated Action statement requirements.
The applicable action is to declare the associated ECCS inoperable. The licensee proposed implementation of the following compensatory actions during the interim period when the one-time revised TS is enforced.
1.
The inoperable channel shall be placed in the condition that will satisfy the logic for allowing injection by the associated ECCS with the reactor steam dome pressure below 410 psig i 15 psig.
2.
Both channels in the other trip system shall be niaintained OPERABLE.
3.
The reactor vessel head vent shall be maintained in the open position.
2.0 EVALUATION An automatic EC S actuation for high drywell pressure requires a permissive by a coincident low reactor steam dome pressure. The steam dome pressure low permissive is a one-out-of-two taken twice logic provided by four independent 9302100529 930203 PDR ADOCK 05000324 p
. pressure transmitters. These transmitters require modification to restore their seismic qualification to the current licensing basis requirements. To
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incorporate the required modifications, CP&L proposed taking these transmitters out of service one at a time.
By telephone, CP&L stated that the B
modifications should take 5 days to complete, but that CP&L is requesting a 7 day allowed outage time to provide a contingency for unexpected problems in performing the modifications.
Brunswick TS 3.3.3 requires a minimum of two operable channels per trio system during operating Modes 1 through 5.
With less than two operable reactor steam dome pressure channels per trip system, the applicable action (Action 31 in Table 3.3.3-1) requires the associated ECCS be declared inoperable.
To avoid the ECCS inoperability, CP&L stated that the inoperable channel (one transmitter taken out for modification) will
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be placed in the condition that will satisfy the logic for allowing injection by the associated ECCS.
By telephone, CP&L clarified that the stated condition is meant to be that the inoperable channel will be placed in trip, thus satisfying the logic for allowing injection by the associated ECCS with the reactor steam dome pressure below 410 psig i 15 psig.
This conservative action will allow the safety equipment to be available upon demand to perform its intended safety function of actuating emergency core cooling in the event of a valid demand.
Further, this action is in accordance with the General Electric Standard Technical Specification which requires placing the inoperable channel in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or declaring the associated ECCS inoperable; and, thus, is acceptable.
The other compensatory action is to maintain the reactor vessel head vent in the open position under the plant operating procedure. This is to avoid any pressure increase above the shutoff head of the ECCS pumps due to an inadvertent actuation of ECCS or vessel inventory heat up which may cause damage to the pumps.
Opening of the reactor vessea head vent during cold shutdown has been previously evaluated and is not a concern with regard to the fission product release outside containment and, thus, is acceptable.
Based on the a nve evalaatic1, the staff concludes that the proposed one-tir.e changes to TS 3.3.3 wi~.1 proside an acceptable level of assurance that the intended safety function of the ECCS instrumentation system will be available upon demand, and are thus acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of North Carolina official was notified of the proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
Pursuar to 10 CFR 51.21, 51.32, and 52.35, an environmental assessment and finding of no significant impact have been prepared and published in the Federal. Reaister on February 2, 1393 (58 FR 6813). Accordingly, based upon the environmental assessment, the staff has determined that the issuance of the amendments will not have a significant effect on the quality of the human environment.
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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 tne 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:
- 1. Ahmed Date: February 3, 1993 i
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