ML20006E077
| ML20006E077 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/30/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20006E075 | List: |
| References | |
| NUDOCS 9002160202 | |
| Download: ML20006E077 (2) | |
Text
._
~
\\
UNITED 8TATES
'[
NUCLEAR REGULATORY COMMISSION j
s wAssmotow. o. c.mos
)
(....
j l
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 29 TO FACILITY OPERATING LICENSE NO. NPF-62 CLINTON POWER STATION, UNIT N0. 1 ILLIN015 POWER COMPANY. ET. AL.
t DOCKET N0. 50-461 t
1.0 INTRODUCTION
i By letter dated October 30, 1987, the licensee for Clinton Unit 1 proposed various changes to the plant's Technical Specifications. The Instrumentation J
and Control Systems Branch has reviewed the requested changes in our area of review and finds two acceptable and three unacceptable as discussed below.
P.0 EVALVATION l
Licensee Package Number 6, Change 2, proposed to refer to Specification 3.6.3.1 in lieu of Specification 3.5.3.1 in Note under " TABLE NOTATIONS" on page 3/4 3-87. We find this change acceptable on the basis that it is purely an editorial change necessary to correct a typographical error.
Licensee's Package Number 6. Change 1, proposed to remove the applicability of the provisions of Specificaf,. ion 3.0.4 in action statements for accident monitoring instrumentation contained in Table 3.3.7.5-1 to permit entry into Operational Conditions 1, 2, or 3 with inoperable channels and while in l
appropriate action statements. This change consists of revisions to Table 3.3.7.5-1 in order to insert exceptions to Specification 3.0.4 into associated
~ ACTION statements. These exceptions would permit entry into OPERATIONAL CONDITIONS 1, 2, and 3, with an accident monitoring instrumentation channel (s) inoperable, as provided in the individual ACTION statements. Although the instrumentation is required to be OPERABLE in OPERATIONAL CONDITIONS I. 2 and 3, the instrumentation is designed and intended to be used to " assess plant and environs conditions during and following an accident" (Ref. Regulatory Guide 1.97). Thus, entry into Conditions 1, 2 and 3 does not necessarily correspond i
to entry into the conditions for which the accident monitoring instrumentation will be needed. Conditions 1, 2 and 3 do correspond to the OPERATIONAL CONDITIONS in which a design basis accident is most likely to be initiated.
Thus, entry into CONDITIONS 1, 2 and 3 should be permitted with the number of OPERABLE channels less than the REQUIRED NUMBER OF CHANNELS requirement, but not with the number of OPERABLE channels less than the MINIMUM CHANNELS OPERABLE requirement (except when the ACTION provides compensatory measures).
Exceptions to Specification 3.0.4 would therefore be inserted into ACTIONS 80, B1 and 82. We find this change acceptable on the basis that it is consistent with staff policy for instrumentation which does not initiate automatic mitigation functions and with current standard technical specifications.
9002160202 900130 ADOCK0500g1 DR
e,,
Licensee's Package Number 4 proposed to change the specific entries and format for trip setpoints and allowable values for timers in Table 3.3.2-2.
Licensee's Package Number 6. Change 3, proposed to revise the action statement applicable to containment /drywell HVAC stack and SGTS exhaust high range radiation monitors in Table 3.3.7.5-1.
Licensee's Package Number 6, Change 4, proposed to delete safety / relief valve acoustic monitors from Tables 3.3.7.5-1 and 4.3.7.5-1.
We find these proposed changes to be unacceptable at this time on the basis that they are not in conformance with the Standard Technical Speci-fications and the licensee has not submitted sufficient technical justification to show that these changes are necessary and acceptable. Due to the generic nature of these proposed changes, they should be evaluated in accordance with the staff policy for generic technical specification changes and revisions to standard technical specifications.
Based on the above evaluation, the staff concludes that two of the proposed changes concerning accident monitoring instrumentation are acceptable. The bases for the staff's acceptance are that the proposed changes (1) do not remove any existing requirements while providing adequate clarification and (2) meet the appropriate guidelines of the Generic Electric Standard TS (NUREG-0123, Revision 3,datedDecember1980).
3.0 ENVIRONMENTAL CONSIDERAY10N Pursuant to 10 CFR 51.21, 51.32, and 51.35, en environmental assessment and findingofnosignificantimpacthavebeenpreparedandpublished(55FR2717) in the Federal Reaister on January 26, 1990.
Accordingly, based upon the environmental assessment, the Comission has determined that the issuance of this amendment will not have a significant effect on the quality of the human environment.
4.0 CONCLUSION
We have 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 Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety to the public, principal Contributor:
F. Burrows, SICB/ DEST Dated: January 30, 1990
.