ML18005A626
| ML18005A626 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 09/30/1988 |
| From: | Buckley B Office of Nuclear Reactor Regulation |
| To: | Utley E CAROLINA POWER & LIGHT CO. |
| References | |
| TAC-67088, NUDOCS 8810060239 | |
| Download: ML18005A626 (3) | |
Text
~h rg aa~ooso~sv eaovso PDR ADQCK 05000400 P
PNU September 30, 1988 Docket No. 50-400 Nr. E.
E. Utley Senior Executive Vice President Power Supply and Engineering 5
Construction Carolina Power
& Light Company P. 0.
Box 1551
- Raleigh, North Carolina 27602 DISTRIBUTION w o enclosure Doc et s
e
'NRC PDR Local PDR PD21 r/f S.
Varga (14E4)
G. Lainas E.
Adensam P. Anderson B. Buckley OGC E. Jordan (tfNBB 3302)
B. Grimes (9A2)
A. Gilbert (8E23)
ACRS (10)
Dear fear. Utley:
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - STEAN GENERATOR TUPE RUPTURE ANALYSIS (TAC NO. 67088)
By letter dated February 1, 1988, Carolina Power 5 Light Company (CP8L) submitted information to demonstrate that the consequences of the design basis steam generator tube rupture (SGTR) event for the Shearon Harris Nuclear Power Plant (SHNPP) are less than the acceptance criteria for calculated doses from radiological releases specified in the Standard Review Plan Section 15.6.3, NUREG-0800.
The submittal was made to satisfy an NRC requirement stated in License Condition 2.C.(5),
Steam Generator Tube Rupture, of the SHNPP Full Power License NPF-63.
The CPSL submittal referenced two Westinghouse
- reports, WCAP-10698 and Supplement 1 to WCAP-10698, accepted by the NRC staff for referencing in plant-specific license applications, and contained plant-specific information requested by the staff and a Westinghouse proprietary report, WCAP-11703, documenting the analysis of a SGTR at SHNPP.
CP8L provided additional information concerning operator action times by letter dated August 25, 1988.
The enclosed Safety Evaluation (SE) discusses the NRC staff's review of the CPGL submittals.
Based on our review and CPSL's commitments to complete the training program associated with SGTR mitigation and verify the boundaries of those operator actions and operator action times assumed in the analysis, we conclude that the methodology and analysis of a SGTR at SHNPP are adequate and acceptable, and that CPSL has satisfied the NRC requirement stated in License Condition 2.C.(5) of License NPF-63.
Verification of operator actions and action times is required prior to startup following the second refueling outage.
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E. Utley Pursuant to 10 CFR 2.790, we have determined that the enclosed SE does not contain proprietary information.
- However, we will delay placing the evaluation in the public document room for a period of ten (10) working days from the date of this letter to provide you with the opportunity to comment on the proprietary aspects only. If you believe that any information in the enclosure is proprietary, please identify such information line by line and define the basis pursuant to the criteria of 10 CFR 2.790.
S incerely, Bart C. Buckley, Senior Project Manager Project Directorate II-1 Division of Reactor Projects I/II
Enclosure:
Safety Evaluation cc w/o enclosure:
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