ML20114A809
| ML20114A809 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/10/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114A805 | List: |
| References | |
| NUDOCS 9208210229 | |
| Download: ML20114A809 (3) | |
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UNITED STATES
'i NUCLE AR REGULATORY CCMMISSION
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METL.[1ALUAT10N BY THE Of flCE Of NUCL[ AR RE AC TOR R[.GlJL Al[QN REl ATf D TO AM[JNDjiENT NO.
73 10 FAC_[LITY OPERATING tlCENSE NO. DPR-80
@D AM[NDMENT NQ.
72 TQ FAC RITY OPERATING LICENSE NO. OPR-82 PA[Ifjc_ GAS AND_((KTjllC COMPANY l
DIABl.0 CANYON NUCLEAR POWER PLANT, UNITS 1 AND 2 D.Q(VET N05. 50-175 AND_50-3L3 1.0 JNTRODUCTION By letter dated December 26, 1991 (Reference LAR 91-08), Pacific Gas and Electric Company (the licensee) submitted a request for changes to the Technical Specifications (TS).
The proposed amendments would relocate the list of containment isolation valves from the TS to plant procedures.
The modified TS would state the requirements for these valves in general terms, in accordance with the guidance of Generic Letter 91-08, dated May 1, 1991.
The NRC staff has reviewed the proposed changes and finds them acceptable.
The staff's evaluation is given below.
2.0 IVAiUATION The licensee has proposed the removal of lable 3.6-1, " Containment Isolation Valves," that is referenced in 15 3/4.6.3.
With the removal of this table, the licensee has proposed to include the following staterent in the Limiting Condition for Operation (LCO) under TS 3.6.3:
Each coritainment isolation valve shall be OPERABLE.
In addition, the licensee has revised the definition of Containment integrity in 1S 1.8, 15 4.6.1.1, the action requirements under TS 3.6.3, and TS 4.6.3.1 j
through 4.6.3.3, to remove all references to Table 3.6-1.
The definition of Containment Integrity and TS 4.6.1.1 refer to 15 3.6.3 for an exception that is now covered by a footnote to the LCO rather than by the table removed f rom j
the TS.
With the removal of the reference to Table 3.6-1, the licensee has proposed to state the exception as:
.., except for valves that are open under aaministrative control as permitted by Specification 3.6.3.
The surveillance requirements of 15 4.6.3.1 through 4.6.3.3 have been revised to state "Each containment isolation valve shall.
"or" each testable power operated or automatic containment isolation valve shall
" rather than stating the requirements in. elation to the valves specified in Table 3.6-1.
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. With the removal of the table of containment isolation valves, the operability requirements have been stated in general terms to apply to all containment isolation valves including those that are locked or sealed closed.
These valves are locked or sealed closed consistent with the regulatory requirements for manually operated valves that are used as containment isolation valves.
Because opening these valves would be contrary to the o)erability requirements of these valves, the following footnote to the LC0 has aeen proposed:
Locked or sealed closed valves may be' opened on an intermittent basis under administrative control.
This. change is consistent with the guidance in Generic Letter 91-08 and is, therefore, acceptable.
In addition, the licensee proposed to change the Bases Section of TS 3.6.3 to define the appropriate _ considerations for opening locked or sealed closed valves on an intermittent basis.
This change is consistent with the guidance of GL 91-08 and is, therefore, acceptable, finally, the licensee has confirmed that component lists removed i
L from the TS have been updated to identify all components for which the TS i
requirements apply and are located-in controlled plant procedures.
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On the basis of its review of this matter, the staff finds that the proposed changes to the.TS for Diablo Canyen Power Plant, Unit Nos. I and 2, are
_ primarily administrative changes that do not alter the requirements set forth in the incisting TS.
However, the applicability of the operability requirements will extend to all _ containment isolation valves as noted in this
-evaluation.
Overall, these changes will. allow the licensce to make corrections and updates-to-the list of_ components for which the:e TS requirements apply, under the provisions that control changes to plant procedures as specified in the Administrative Controls Section of the TS.
Therefore, the staff finds that the proposed TS. changes are acceptable.
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STATE CONSULTATION In acccrdance_with-.the Commission's regulations, the California State official was-notified.of the proposed issuance of the amendments.
The State official hsd no comments.
4.0 ENVIRONMENTAL CONSIDERATION
These amendments change a requirement with respect to the installation or use of a-facility component 1ocated within the restricted area as defined.in L
10'CFR Part_20 and changes _ surveillance-requirements.
The NRC staff has
' determined that the amendments involve no significant increase in the amounts,
- and no significant change in the types, of any effluents that may be released offsite, and.thatt 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 considera-tion, and there has been no public comment on such finding (57 FR 13135).
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., Accordingly, the c.:.dments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSIM The Commission 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, (2) such activities will be conducted in complience with the Commissicn's regulations,
. and (3)-.the issuance of the amendment still not be inimical to the common defense and security or to the health and safety of the public.
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Principal Centributor:
C. Regan Date: August 10, 1992
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