ML20086U100
| ML20086U100 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/28/1984 |
| From: | Howe P CAROLINA POWER & LIGHT CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20086U103 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.15, TASK-TM GL-83-02, GL-83-2, NLS-84-065, NLS-84-65, NUDOCS 8403070157 | |
| Download: ML20086U100 (2) | |
Text
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NLS-84-065 Carolina Power & Light Company FEB 281984 Director of Nuclear Reactor Regulation Attention:
Mr. D. B. Vassallo, Chief Operating Reactors Branch No. 2 Division'of Licensing United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS.. 50-325 & 50-324/ LICENSE NOS. DPR-71 & DPR-62 SUPPLEMENTAL REQUEST FOR LICENSE AMENDMENT NUREG-0737 TECHNICAL SPECIFICATIONS
Dear Mr. Vassallo:
SUMMARY
p In~accordance with the Code of Federal Regulations, Title 10, Part 50.90 and Part 2.101, Carolina Power & Light Company (CP&L) hereby r(quest revisions to the Technical Specifications (TS) for the Brunswick Steam Eleu.cic Plant (BSEP), Unit Nos. 1 and~2.
These revisions are a supplement to our requests dated March 16, 1982, June 23, 1983, and September 6, 1983 and supersede those
'.i~
TS pages provided in our September 6, 1983 submittal. The September 6, 1983 submittal provided the Brunswick-1 and Brunswick-2 TS pages for Item 9,
- isolation of HPCI and RCIC modification (NUREG-0737, Item II.K.3.15), of the NRC's Generic Letter No. 83-02 dated January 10,-1983.
DISCUSSION Upon review, it was discovered that the method used to incorporate the HPCI and RCIC system isolation time delays into response times (items 4.a and 4.b of Table 3.3.2-3) in our h tember 6, 1983 submittal was incorrect. There are
.wo isolation valves each. the HPCI and RCIC system; one is AC powered and the other is DC powered. The response times provided in our September 6, 1983 submittal assumed'that the DC isolation valve fails and that no offsite AC power is available.to the AC valve. Therefore, the response time was based on a 10 second diesel start sequence, after which a 3 to 7 second circuitry time C
delay commences, resulting in a summation of the diesel generator start sequence and the circuitry time delays.
In~ actuality, the isolation circuitry for:both the AC and DC isolation valves is continuously powered by the station 4W Lelectric batteries. Upon receipt of an isolation signal, the diesel 4
_ generators and the AC valve circuitry actuate' simultaneously, not sequentially. The diesel generator start sequence encompasses the m
M simulttneous 3 to 7 second HPCI/RCIC system isolation circuitry time delay, yielding a maximum system response time of 10 seconds. A'13 second isolation of HPCI/RF C system steam line breaks has been analyzed and found a::eeptable.
Therefore, i response time if less than or equal to 13 seconds is provided for Items 4.'a.1 and 4.b.1 in Table 3.3.2-3.
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Mr. D. B. Vassallo 2-Items 4.a.2 and 4.b.2 have been added to Tables 3.3.2-1, 3.3.2-7, 3.3.2-3, and 4.3.2-1 of the Brunswick-1 and Brunswick-2 TS to establish Limiting Conditions
- for Operation and Surveillance Requirements for the HPCI/RCIC isolation system t a delay relays.L The 3 to 7 second time delay range (Items 4.a.2 and 4.b.2
. of Table 3.3.2-2).is based on the model. Technical Specifications given as
- guidance in Generic Letter 83-02.
The BWR Owners' Group Evaluation enclosed in our. December 31, 1980 submittal to Mr. D. G. Eisenhut concerning post-TMI requirements is the' technical basis for the allowable time delay rangs of 3 to 12 seconds.- Your staff has previously reviewed this methodology and provided
. approval.in your letter of. July 28, 1982.
Administrative Information Enclosed are revised TS pages for Brunswick-1 and Brunswick-2. These pages supersede the same numbered TS pages provided in our September 6, 1983 l
submittal. Since this request relates to NUREG-0737 requirements and is a supplement to our March 16, 1982 request,.we have determined that no additional license amendment fee is required.
.Should you have any questions concerning this submittal, please contact a 3
L member of our Licensing staff.
[
Yours very truly, O '( d-P. W. Howe f~
Vice President f,
Brunswick Nuclear Project fp MAT / lev (9488 MAT)
Enclosures P. W. Howe, having been first duly sworn, did depose and say tha't the "information contained herein is true and correct to the best of his
- information, knowledge acd belief;:and the sources of his information are
' officers, employees, contractors, and agents of Carolina Power & Light
- Company.
L)L Notary (feal)
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'My commission expires:
'cc:
Mr. Dayne H. Brown
' Radiation Protection Branch
' Division of Facility Services Department of Human Resources Mr. D. 0. Myers.(NRC-BSEP)
Mr. J. P. O'Reilly (NRC-RII)
Mr. M. Grotenhuis (NRC);
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