ML18005A610
| ML18005A610 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/29/1988 |
| From: | Buckley B Office of Nuclear Reactor Regulation |
| To: | Utley E CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML18005A611 | List: |
| References | |
| TAC-68341, NUDOCS 8810030143 | |
| Download: ML18005A610 (3) | |
Text
P+R 01 43 ggOQ 88100g DOC< 050QQypp ii PNU Docket No. 50-400 Mr. E.
E. Utley Senior Executive Vice President Power Supply and Engineering 5
Construction Carolina Power 5 Light Company Post Office Box 1551 Raleigh, North Carolina 27602 DISl RIBUTION
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Varga (14E4)
G. Lainas E. Adensam P. Anderson B. Buckley OGC E. Jordan (MNBB 3302)
B. Grimes (9A2)
W. Hodges (8E23)
ACRS (10)
Dear Mr. Utley:
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - NATURAL CIRCULATION COOLDOWN ANALYSIS (TAC NO. 68341)
By letter dated May 17, 1988, Carolina Power 5 Light Company (CPSL) submitted a Westinghouse analysis entitled "Shearon Harris Nuclear Power Plant (SHNPP)
Natural Circulation Cooldown Evaluation Program Report,"
WCAP-11810, to show the:capability of SHNPP to successfully achieve cold shutdown conditions under the requirements of Branch Technical Position (BTP)
RSB 5-1.
This submittal was made to satisfy an NRC requirement documented in Section 5.4.7.5 of Supple-ment 4 to the Shearon Harris Nuclear Power Plant Safety Evaluation Report (SSER4) and fulfilla commitment made in a CP8L letter to the NRC dated August 31, 1982.
As stated in SSER4, satisfactory resolution of the issue is required prior to startup after the first refueling outage.
Specifically, the staff requires CP8L to demonstrate the applicability of the Diablo Canyon natural circulation cooldown test results to SHNPP.
The Westinghouse
- report, WCAP-11810, includes (a) a qualitative comparison of the designs of the Diablo Canyon plant and SHNPP to demonstrate the thermal and hydraulic similarity of the two, (b) a cold shutdown scenario for SHNPP using the minimum equipment available for the cooldown under the constraints of BTP RSB 5-1, and (c) a quantitative thermal-hydraulic computer code (TREAT) analysis of the scenario to evaluate and justify the SHNPP cold shutdown capabilities under the requirements of BTP RSB 5-1 for natural circulation cooldown and boron mixing in the reactor coolant system.
By letter dated August 31,
- 1988, CPSL provided a response to staff questions on the natural circulation analysis and procedures.
Based on our review of the CPSL submittals and CP5L-commitments to modify existing procedures as discussed in the NRC staff safety evaluation, we conclude that CPSL has demonstrated that Diablo Canyon natural circulation tests are applicable to SHNPP, and that SHNPP is in compliance with BTP RSB 5-1.
We conclude, therefore, that CPEL has satisfied the NRC requirement documented in Section 5.4.7.5 of Supplement 4 to the SHNPP SER.
Mr: E. E. Utley The licensee has scheduled implementation of modified operating procedures as identified in the attached safety evaluation by prior to initial criticality.
This implementation date is acceptable to the staff.
S incere ly, Enclosur e:
Safety Evaluation cc w/enclosure:
See next page Bart C. Buckley, Senior Project Manager Project Directorate II-1 Division of Reactor Projects I/II
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