ML20070K070
| ML20070K070 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/11/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K061 | List: |
| References | |
| NUDOCS 9103180294 | |
| Download: ML20070K070 (3) | |
Text
_ _
s:
ff,.,I*g UNITED STATES y
g NUCLE AR REGULATORY COMMISSION 3m WASHINGTON, D. C. 20565
\\...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION EDPORTING AMEN 0 MENT NOS.119 AND gg TO FACILITY OPERATING LICENSE NOS. OPR-70 AND DPR-75 PUBLIC SERVICE ELECTRIC & GAS COMPANY PHILADELPHIA ELECTRIC COMPANY DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY SALEM GENERATING STATION, UNIT NOS 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
By letter dated December 27, 1990, Public Service Electric & Gas Company (PSE&G) requested an amendment to Facility Operating License Nos. OPR-70 and DPR-75 for the Salem Generating Station, Unit Nos. I and 2.
The proposed amendments would delete Technical Specification Surveillance Requirement 4.7.1.2.c.
This surveillance requires verification of the l
flow path from the Auxiliary Feedwater Storage Tank to each steam generator before entering Mode 3 following each cold shutdown. Also, the locked open valve list of Surveillance Requirement 4.7.1.2.a.4 would be relocated to the Bases section and a statement added to that section requiring all the manual valves in the flow path to be locked open.
A statement would be added to the valve list thet a spool piece may be used as an equivalent to a locked open valve.
2.0 EVALUATION l
The auxiliary feedwater system at Salem 1 and 2 has two electric motor driven and one turbine driven auxiliary feedwater pumps installed.
Technical Specification Surveillance Requirement 4.7.1.2.c requires the auxiliary feedwater system to be demonstrated operable prior to entry to Mode 3 by performing a flow test to verify normal flow paths to each steam generator.
Because of the exact wording of the surveillance requirement, i.e., "... verify the normal flow paths from the Auxiliary Feedwater Storage Tank to each of the steam generators.", some questions have been raised about compliance because the turbine driven auxiliary feedwater pump can not be operated prior to entry into Mode 3.
PSE&G has proposed to delete this surveillance requirement from the technical specifications.
During restart from a cold shutdown condition, Salem 1 1
9103180294 910311 1
{DR ADOCK0500g2
%g e
2 and 2 use the motor driven auxiliary feedwater pumps to supply water to the steam generators.
This normal operation verifies that flow paths exist from the Auxiliary Feedwater Storage Tank to the steam generators via the motor driven auxiliary feedwater pumps. When sufficient steam pressureisavailable(greaterthan750psig),theturbinedriven auxiliary feedwater pump is tested on recirculation in accordance with the inservice test program. This test of the turbine driven auxiliary feedwater pump verifies flow from the Auxiliary Feedwater Storage Tank through the sur9 Also, Technical Specification Section 3.7.1.2 requires the flow patis to be operable. Because there is a requirement in the technical specifications that the flow paths be operable and they are verified during the normal startup sequence, the staff finds this proposed change to delete Technical Specification Surveillance Requirement 4.7.1.2.c acceptable.
Technical Specification Surveillance Requirement Section 4.7.1.2.a.4.
contains the list of manually operated, locked open valves in the flow paths to the steam generators, pSE&G has prososed-to replace the locked i
open valve list with the statement, " Verify tie manuel main +.enance valves in the flow path to each steam generator are locked open." The valve list would be placed in the Bases, Section 3/4.7.1.2. along with a statement that "A spool piece consisting nf a length of pipe may be used as an equivalent to a locked open manual valve." The proposed change provides the necessary requirement to assure that the valves will be properly positioned, without specifying the individual valves. By including the valves in the Bases Section 3/4.7.1.2, adequate identification of the valves in the flow p,ath is maintained. The inclusion of the statement, "A spool piece consisting of a length of pipe may be used as an equivalent to a locked open manual valve.' will provide some flexibility in the maintenance area. This allowance does not change the requirement to maintain the flow paths to the steam generators.
In addition, because the replacement of a valve with a spool piece is a change to the facility as described in the Upd:ted Final Safety Analysis Report, an evaluation in accordance with 10 GR 50.59 will be performed to assess the safety significance of the action. The staff finds the changes to Technical Specification Section 4.7.1.2.a.4 and Bases Section 3/4.7.1.2 to be acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
These amendments involve a change to a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes' to the surveillance requirements. The staff has determined that the amendments involve no l
significant increase in the amounts, and no significant change in the l
types, of any offluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Comission has previously issued a proposed finding that -
the amendments involve no significant hazards consideration and there has been ro public coment on such finding. Accordingly, the amendments
l
]
i 3
I i
meet the eligibility crit 91a for categorical exclusion set forth in 10 CFR51.22(c),9).
Pursuant to 10 CFR 51.??(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
A.0 CONCLUSION The Comission made a proposed determination-that the amendments involve no significant hazards consideration which was published in the rederal l
Register (56 FR 4872) on February 6,1991 and consulted with the State of flew Jersey.
No public coments were received and the State of New Jersey did not have any comments.
The staff 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, and (2) such activities will be conducted in compliance with the Comission's regulations and the issuance of the amendments will not be inimical to the common defense and security nor to the health and safety of the public.
Dated:
March 11, 1991 i
Principal Contributor: James Stone i
6 l
i l
i i
I l
t j.
.--...a-..-
.--,,.....__.._.._.-.-,,,._.,.,~,,._.-_....,,_..u....~~_
. -