NUREG-1431, Safety Evaluation Supporting Amend 60 to License NPF-63
| ML18011A985 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 08/01/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18011A984 | List: |
| References | |
| RTR-NUREG-1431 NUDOCS 9508090156 | |
| Download: ML18011A985 (6) | |
Text
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2055&OOOI SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO.
60 TO FACILITY OPERATING LICENSE NO.
NPF-63 CAROLINA POWER 5 LIGHT COMPANY
-SHEARON HARRIS NUCLEAR POWER PLANT UNIT I DOCKET NO. 50-400
1.0 INTRODUCTION
By letter dated March 30,
- 1995, as supplemented July 6,
- 1995, the Carolina Power
& Light Company (the licensee) submitted a request for changes to the Shearon Harris Nuclear Power Plant, Unit 1
(SHNPP),
Technical Specifications (TS).
The requested changes would revise the Emergency Diesel Generator (EDG) surveillance requirements contained in TS 3/4.8. 1. 1.2 to be consistent with NUREG-1431, "Standard Technical Specifications, Westinghouse plants,"
and to eliminate the need for duplicate EDG testing being performed to satisfy the requirements of the Station Blackout Rule and the Maintenance Rule.
The elimination of duplicate testing will reduce the overall wear and stress on engines and thus result in an increase in long-term engine reliability for the EDG.
The safety function of the EDGs is to supply ac electric power to plant safety systems whenever the preferred ac power supply is unavailable.
The July 6, 1995, submittal did not change the initial no significant hazards consideration determination; it contained clarifying information only.
3.0 EVALUATION The current surveillance requirement (SR) 4.8. 1. 1.2.e requires in part that the EDG be synchronized to its appropriate emergency
- bus, loaded to an indicated 6200-6400 kW in less than or equal to 60 seconds, and operate for at least 60 minutes.
The proposed amendment would delete the words "in less than or equal to 60 seconds,"
following the words "loaded to an indicated 6200-6400*** kW."
The rapid loading of the EDG to 6200-6400 kW in 60 seconds produces high thermal stresses in the engine piston, cylinder liners and cylinder heads, and contributes to accelerated wear of these and other engine components.
The ability of the EDG to start and load rapidly is adequately demonstrated by 18-month surveillance testing currently being performed to satisfy surveillance requirement 4.8. 1. 1.2.f.6.b.
This test verifies that the EDG will start on an auto-start signal, energizes the auto-connected emergency loads through the sequencer and operates for greater than or equal to 5 minutes, while maintaining steady-state voltage and frequency at 6900 i 690 volts and 60 t 1.2 Hz.
The staff finds the proposed change to be consistent with NUREG-1431 and Generic Letter 84-15, "Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability," and therefore, is acceptable.
The current SR 4.8. 1. 1.2.f. 1 requires that each EDG be inspected every 18 months in accordance with procedures that have been prepared in accordance with the TDI Owners Group's recommendations.
The proposed change would modify 9508090i5b 95080i PDR ADOCK 05000400 P
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2 by relocating this surveillance requirement to the Shearon Harris'DG reliability and availability program, and the licensee has stated that any changes to this program will be controlled by the 10 CFR 50.59 process.
The staff concurs that these inspection and testing provisions can be controlled by the EDG reliability and availability program because sufficient surveillance requirements are retained in the TS to demonstrate the functional capability of the diesel generator.
Further, this change does not alter the surveillance requirements because the subject TS will be relocated in their entirety to the EDG reliability and availability program.
Therefore, the staff finds that the proposed relocation of the SV from the TS is acceptable.
The current SR 4.8.1.1.2.f.6.c requires that, by simulating a loss of offsite power (LOOP) in conjunction with a safety injection test signal, the licensee verifies that all diesel generator trips (except for engine overspeed, loss of generator potential transformer circuit, generator differential, and emergency bus differential) are automatically bypassed.
The licensee has proposed to change to this surveillance requirement by deleting the word "upon" and inserting the phrase "on simulated or actual" and relocate it as separate SR 4.8.1.1.2.f. 13.
Since the licensee will continue to perform this SR, the staff finds the above proposed change to be acceptable.
- Moreover, the modified format of this SR is consistent with the format used in NUREG-1431.
The current SR 4.8.1.1.2.f.7 requires that within 5 minutes of shutting down the EDG following an 24-hour endurance test run, a simulated LOOP in conjunction with a safety injection signal surveillance test be conducted.
The licensee has proposed to separate the 5-minute hot restart test from the 24-hour endurance test, to eliminate the requirement for the LOOP in conjunction with a safety injection signal test following the 24-hour loaded
- run, and to add.a new surveillance requirement of a simple hot restart test following a 2-hour loaded run of the EDG.
The revised surveillance requirement will verify EDG hot restart capability by starting the EDG and verifying that it will attain rated voltage and frequency within the required time.
The purpose of the ED6 hot restart surveillance is to demonstrate the functional capabilities of the EDG to restart from the full-load temperature conditions.
The new SR 4.8.1. 1.2.f. 14 would provide adequate demonstration that the EDG has the restart capability from full-load temperature conditions.
This modified surveillance requirement of the EDGs has been examined and accepted by the NRC staff in NUREG-1431.
- Further, the hot restart test, the LOOP in conjunction with a safety injection signal test, and 24-hour endurance test objectives will continue to be met at the SHNPP; and thus decoupling the tests would result in improved scheduling flexibilitywith no reduction in demonstration of EDG operability.
Based on the above, the staff finds the proposed changes to be acceptable.
The current SR 4.8.1.1.2.f.8 requires verification that auto-connected loads do not exceed the continuous rating of the EDG.
The licensee has proposed to delete this requirement from the TS and relocate this requirement to the plant test procedures.
This verification will continue to be performed periodically per refueling cycle by testing, design verification, or a combination of both to insure that the auto-connected loading has not changed and that the loads
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do not exceed the continuous rating of the EDGs.
On this basis, the staff concludes that this change does not alter the surveillance requirements because the subject TS will be relocated in its entirety to the plant test procedures and any changes to the plant test procedures are subjected to the 10 CFR 50.59 review process.
Therefore, the staff finds that the proposed relocation of this requirement from the TS is acceptable.
The current SR 4.8. 1. 1.2.f. 10 requires verification that the EDG will not start when a non-bypassed trip condition exists or when the EDG is locked out by the selection of maintenance mode.
The licensee has proposed to delete this requirement from the TS and relocate this SR to the EDG reliability and availability program.
The maintenance mode selector switch is designed to prevent the EDG operation while the switch is in the maintenance mode.
The licensee contends that though important to personnel
- safety, the mode selector switch has no plant safety-related function and thus needs not be included as a
SR in the TS.
The actual activation of this maintenance feature is evidenced by observing the indicating light on the EDG control panel and the extension of the shutdown cylinder (fuel racks in the "no fuel" position).
The staff concurs with the licensee that the maintenance mode switch does not perform any safety function and therefore the proposed removal of its SR to the EDG reliability and availability program is acceptable.
With regard to the verification of EDG shutdown when non-bypassed trip conditions exists, the licensee states that the EDG reliability and availability program requirements will ensure the EDG to shut down when a non-bypassed trip condition is received and to remain locked-out from any start signal.
Thus, monitoring and testing activities to verify the EDG system/subsystem functions are within the scope of these programs and therefore, inclusion of these surveillance requirements in TS is an unnecessary duplication.
Hased on the above, the staff concludes that the proposed change does not alter the surveillance requirements because the subject TS will be relocated in their entirety to the EDG reliability and availability program and any change to this program are controlled by the 10 CFR,50.59 process.
Moreover, this change is consistent with NUREG-1431.
Therefore, the staff concludes that SR 4.8. 1. 1.2.f. 10 may be relocated from the TS.
4.0 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.
5.0
'ENVIRONMENTAL 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 the 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 individual 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 (60 FR 20515).
Accordingly, the amendment meets the eligibility criteria 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'e prepared in connection with the issuance of the amendment.
6.0
~NLII 7he 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 Contributors:
- 0. Chopra N.
Le Date:
August 1, 1995
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