ML20245F634
| ML20245F634 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/24/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245F603 | List: |
| References | |
| NUDOCS 8905020446 | |
| Download: ML20245F634 (4) | |
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UNITED STATES
'8 NUCLEAR REGULATORY COMMISSION o
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WASHINGTON, D. C. 20656 i
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NOS. 92 AND 67 TO FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75
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PUBLIC SERVICE ELECTRIC & GAS COMPANY P_ 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 November 27, 1985, Public Service Electric & F*s Company (PSE&G) requested an amendment to Facility Operating License Nos. DPR-70 and DPR-75 for the Salem Generating Station, Unit Nos. 1 and 2.
The proposed amendments would amend Technical Specification 3.6.3, Containment Isolation Valves, for Salem Units 1 and 2.
The proposed amendment sought a modification of the wording in the Limiting Condition for Operation (LCO) as well as changes in the containment isolation valve table (Tech. Spec.
Table 3.6-1).
After an initial staff. review, the staff concluded that the LC0 wording change was unacceptable and that the containment isolation valve table modification was acceptable vith one exception. PSE&G had included two
(.ontainment outboard series' isolation valves in the table (CC117 and CC118. Component Cooling to the Reactor Coolant Pumps) with the intention of using either one or the other of these outboard valves as the isolation valve for a particular containment penetration. The staff stated that only the valve which is closest to the containment (CC118)
I should be included in Tech. Spec. Table 3.6-1.
In order to gain approval of this license change request, PSE&G on February 15, 1989 resubmitted the requested change removing valve CC117 from Tech Spec Table 3.f I for both Salem Units 1 and 2, and withdrawing their proposed change of the wording in the LCO.
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.o L, 2.0 EVALUATION The. original November 27, 1985 request contained the following proposed-changes to TS 3.6.3 and associated ACTION statements.
(a)~Descriptionofchange:
The char.ge would allow an inoperable isolation valve to satisfy its OPERABILITY requirements if the valve i
is maintained closed to isolate the affected penetration.
Staff evaluation:
The proposed TS change would consider an inoperable containment isolation valve to be OPERABLE, i.e., the limiting condition for operation to be satisfied, if the valve is administrative 1y maintained closed.
Consequently, fluid lines could be isolated, and administrative 1y maintained closed, without ever having to declare that a limiting condition for operation was not being met or that an ACTION statement has to be entered. Although, isolating a fluid line and administrative 1y maintaining that condition is an acceptable approach for meeting the current LCO, having to enter an ACTIGN statement is preferable from an operational safety standpoint. Operations personnel would be more aware of potential safety concerns by having to take remedial action, and documenting it, to reestablish compliance with a LCO.
Consequently, the staff found the proposed changes to TS 3.6.3 unacceptable.
PSE&P, in their February 15, 1989 resubmittal, 1
withdrew this proposed change.
The origieal November 27, 1985 request contained the following proposed changes to Technical Specifications (TS) Table 3.6-1, containment Isolation Valves.
(a) Description of change: Addingvalves(aslistedinthesubmittai) to TS Table 3.6-1 because they are considered to be containment isolation valves and s bject to Type C (local leakage rate) testing.
Staff evaluation:
These valves were inadvertently omitted from Table 3.6-1 and the Type C testing program. Adding these valves to the Type C testing program is acceptable.
(b) Description of change:
Changing the classification of certain valves (as listed in the submittal) such that they are required to be Type C tested, rather than being excepted from Type C testing.
Staff evaluation: Adding valves to t% Type C testing program is I
acceptable.
(c) Description of change:
Designating certain valves (as listed in the submittal) in the steam generator blowdown and steam generator l
blowdown sampling lines as not being subject to Type C testing.
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Staff evaluation: These valves are connected to the secondary side
.of!the-steam generator, which constitutes a closed system inside containment which is not postulated to rupture during a LOCA..Thus, the subject valves will not be exposed to containment atmosphere during a LOCA and do not constitute potential containment atmosphere-leak paths. Although Appendix J to 10 CFR Part 50 requires _ main steam-system (e.g.,mainsteamand-feedwater)isolationvalvesinboiling
' water reactors to be Type C tested (Section II.H.4'of Appendix J), it does not. require such valves in pressurized water reactors, as the Salem. facility, to be. Type C tested. Therefore, it is acceptable to delete'the' subject valves from the Type C testing program.
(d). Description of change: Deletingvalves11(21)'SS93,.12(22)SS93, 13(23) SS93, and 14(24) SS93 from TS Table 3.6-1.
Staff evaluation: The staff determined that these valves are not f
required to be containment isolation valves and may be deleted from the table.- Since they are not containment isolation valves, they are not subject to Type C testing.
Further, the staff found that valve CC117 is not a containment isolation valve.- As a further clarification to that SER, the staff finds that-the
' valve CC117.may be deleted from TS Table 3.6-1 and removed from the Type i
C testing program.
The valve was deleted from table in the February 15, j1989,resubmittal.
Therefore, the staff finds the proposed changes as described above to be acceptable.
.In addition, administrative clarifications and typographical corrections were made to the licensee's incoming technical specifications pages and
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bars were added to those pages to show the changes.
3.0 ENVIRONMENTAL-CONSIDERATION
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These^ amendments involve a, change to a requirement with respect.to the.
I installation or use of a facility component located within the restricted area as' defined in 10 CFR Part 20.- The staff has determined that the amendments involve no significant' increase in the amounts, and no
- significant changt in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant
-hazards consideration and there has been no public comment on such finding. Accordingly, the amendments meet the eli categorica1' exclusion set forth in 10 CFR 51.22(c)gibility criteria for (9). Pursuant to 10 CFR j
51.22(b),noenvironmentalimpactstatementorenvironmentalassessment need be prepared in connection with the issuance of the amendments.
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' 4.0- CONCLUSION
.The Comission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (51 FR 24261) on July 2,1986. and consulted with the State of New Jersey..No public comente were received and the State of New Jersey did not have any coments.
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The staff has concluded, based on the considerations discussed above, 4
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 Commission's regulations and the issuance of the amendments will not be I
inimical to the comon defenst and security nor to the health and safety of the public.
Principal Contributor: Donald Fischer Dated: April 24, 1989
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