ML19256G495
| ML19256G495 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/17/1979 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| TAC-11116, NUDOCS 7912310392 | |
| Download: ML19256G495 (4) | |
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DEC 171979 MEMORANDUM FOR:
D. Ziemann, Chief Operating Reactors Branch #2 Division of Operating Reactors FROM:
G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
SUBJECT:
SAFETY EVALUATION REPORT, FIRE PROTECTION PROGRAM REVIEW - MILLSTONE 1 (TAC 11116)
Plant Name: Millstone 1 Licensee: Northeast Utilities Docket No.: 50-245 Responsible Branch: ORB #2 Project Manager:
J. Shea Review Branch:
PSB Requested Completion Date: August 31, 197.'
Status: See Enclosure 1 Our initial Safety Evaluation Report (SER) dealing with fire protection at Millstone 1 was issued on September 26, 1978.
In Section 3 of the SER certain items were identified as incomalete and requiring further information from the licensee and evaluation by the staff. We have completed our review of information dealing with incomplete item 3.2.2, Fire Hose Station Evaluation, as provided in licensee response of July 31, 1979.
The results of our review are enclosed. Enclosure 1 is a status of the incomplete items and Enclosure 2 is our evalua-ion of this item.
'. h
/G. Lainas, Chief Plant Systems Branch Division of Operating Reactors
Contact:
L. :erderian, X27600
Enclosures:
1.
Resolution of Incorplete Items - Status 2.
Evaluation of Iter 3.2.2 -
Millstone 1
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7912310 '3] y
L D. Ziemann DEC 171973 cc w/ enclosures:
D. Eisenhut R. Vollmer W. Gammill V. Benaroya P. Matthews G. Lainas R. Ferguson L. Derderian T. Wambach J. Shea PSB Reviewers M. Antonetti, BNL R. Hall, BNL 4
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t RESOLUTION OF INCOMPLETE ITE.S - STATUS MILLSTONE UNIT 1 Staff Evaluation Licensee Response Due 3.1.4 Water Suppression Systems Ongoing 3.1.5 Gas Suppression Systems Cocplete 3.1.19 Safe Shutdown Modifications (SEP Deferred) 3.2.1 Smoke Detection Systems Test In ornation 1/
3.2.2 Fire Hose Station Evaluation Co :plete 1/ Licer.see is awaiting our evaluation o? prop: set e-h::d - (ssa Yarkee Rowe, 50-29, letter dated October 3,1979).
P00RBRBINIL 1657 137
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3.0 EVALUATION The following provides our evaluation of the incomplete item.
Numbers in paranthesis following each heading refer to the sections or our previoJsly issued SER which address this incomplete item.
3.1 Fire Hose Station Evaluation (3.2.2)
Our SER noted that hose stations would be verified to be capable of supplying a pressure of 65 psig at the nozzle under flowing condi tions. Larger pipe sizes would be provided if required to provide a hose nozzle pressure to insure adequate hose stream throw.
By letter dated July 31, 1979, the licensee stated that a pressure test had been performed at Hose Station Nos. 44 and 45. These stations are located at the 108' level in the reactor building and represent the most severe condition for pressure considerations.
The test results indicate that the pressure at the nozzle would be 72 psig and 65 psi.g respectively.
We find that this test verifies that the fire hose stations will supply at least 65 psig at the hose nozzles.
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