ML20235Q868
| ML20235Q868 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/23/1989 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235Q871 | List: |
| References | |
| NPF-62-A-018 NUDOCS 8903030062 | |
| Download: ML20235Q868 (2) | |
Text
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CONTAINMENT SYSTEMS DRYWELL AIR LOCKS SURVEILLANCE REQUIREMENTS 4.6.2.3 Each drywell air lock shall be demonstrated OPERABLE:
a.
Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following each closing, except when the air lock is being used for multiple entries, then at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, by verifying seal leakage rate less than or equal to 2 scf per hour when the gap between the door seals is pressurized to 3.0 psig, b.
By conducting an overall air lock leakage test at 3.0 psig and verifying that the overall air lock leakage rate is within its limit:
1.
Each cold shutdown if not performed within the previous 6 months #
2.
Prior to establishing DRYWELL INTEGRITY when maintenance has been performed on the air lock that could affect the air lock sealing capability.
c.
By verifying, prior to drywell entry if not performed within the past 18 months, that only one door in the air lock can be opened at a time.
~
$o wo SU OO ma S.
- At least once per 18 months, the air lock will be pressurized to 19.7 psid prior l
SS to conducting the overall air lock test.
m a. a.
I CLINTON - UNIT 1 3/4 6-17 Amendment No.18 1
- l (8) Post-Fuel Loading Initial Test Program (Section 14, SER, SSER 5 j
and SSER 6)
)
Any changes to the initial test program described in Section 14 of the FSAR made in accordance with the provisions of 10 CFR 50.59 shall be reported in accordance with 50.59(b) within one month of such change.
(9) Emergency Resaonse Capabilities (Generic Letter 82-33, Supple-ment 1 to NUREG-0737, Section 7.5.3.1, SSER 5 and SSER 8, and Section 18, SER, SSER 5 and Safety Evaluation Dated April 17, 1987) a.
IP in accordance with the commitment contained in a letter dated December 11, 1986, shall install and have operational separate power sources for each of the fuel zone level channels as provided for in Regulatory Guide 1.97 prior to startup following the first refueling outage.
b.
IP shall submit a detailed control room design final supple-mental summary report within 90 days of issuance of the 1
full power license that completes all the remaining items
' O ntified in Section 18.3 of the Safety Evaluation dated April 17, 1987.
D.
The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70.
These include:
(a) an exemption from the requirements of 10 CFR 70.24 for the criticality alarm monitors around the fuel storage area; (b) an exemption from the requirements of Appendix A to 10 CFR Part 50, General Design Criterion 61 to per-mit a schedular deferral of completion of preoperational testing of a portion of the Fuel Handling System until prior to offloading fuel s
from the reactor vessel (Section 14, SSER 8); (c) an exemption from
(
the requirement of paragraph III.D.2(b)(ii) of Appendix J, substitut-ing the seal leakage test at Pa of paragraph III.D.2(b)(iii) for the entire airlock test at Pa of paragraph III.D.2(b)(ii) of Appendix J l
when no maintenance has been performed in the airlock that could l
affect its sealing capability (Section 6,2.6 of SSER 6); and (d) an exemption from the requirement of paragraph III.C.3 of Appendix J, exempting the measured leakage rates from the main steam isolation valves from inclusion in the combined leak rate for the local leak rate tests (Section 6.2.6 of SSER 6).
The special circumstances regarding each exemption, except for Item (a) above, are identified in the referenced section of the safety evaluation report and the I
supplements thareto.
l l
l l
Aniendrent No.18 1
J