ML20116A115
| ML20116A115 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 04/22/1985 |
| From: | Spangenberg F ILLINOIS POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| U-0887, U-887, NUDOCS 8504240350 | |
| Download: ML20116A115 (2) | |
Text
U-0887 L30- 85(04-22)-L' 1A.120
.IILIN018 POWER COMPANY IP CLINTON POWER STATION, P.o. BOX 678 CLINTON, ILLINOIS 61727 April 22, 1985 Docket No. 50-461
~
Director of Nuclear Reactor Regulation
-Attention:
Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Clinton Power Station, Unit 1
-Periodic Low Pressure Leakage Testing of the Drywell (SER Confirmatory Issue #66)
Dear Mr. Schwencer:
Illinois Power Company (IP) Letter U-0671, dated September 30, 1983, provided the Staff with IP's endorsement of Licensing Review Group-II's:(LRG-II) Position Paper 3-CSB, entitled " Periodic Low Pressure Leakage Testing of the Drywell", and a Clinton-specific basis for use of the Drywell Purge system for pressure control during plant operating modes above cold shutdown (i.e. Modes 1, 2, and 3 as defined by Technical Specifications). The NRC Staff provided their evaluation of the-LRG-II position on this issue via a letter to D. L. Holtzscher
'(Chairman, LRG-II), dated January 17, 1985. The Staff's evaluation concluded that the drywell low pressure leakage testing frequency of 18 months (per Standard Review' Plan (SRP), Section 6.2.1.1.c, Appendix A.
Revision 5) should be maintained.
IP has reevaluated'this issue, as it applies to CPS. Based on this reevaluation, IP commits to performance'of the drywell low pressure.
leakage test, in accordance with SRP Section 6.2.1.1.c, Appendix-A, Revision 5,~every 18 months or during each refueling outage. The conditions for this test (i.e., initial test pressure corresponding to that pressure which maintains Suppression Pool Water level slightly above the elevation of the first row of vents) and the acceptance
. criteria (i.e., measured leakage be less than or equal to 10% of the allowable leakage for the Drywell) are as previously described in LPG-II Position Paper 3-CSB (in compliance with the criteria of SRP Section 6.2.1.1.c, Appendix A, items B.2.b and B.2.c respectively). This position is consistent with that taken by the other LRC-II members.
Enclosure #1 to the LRG-II paper provided a proposed "Drywell Bypass Leakage" Technical Specification. This Technical Specification will be modified for CPS to accommodate e test frequency of every 18 months, or during each refueling outage and will be submitted to the Staff as part of the CPS Technical Specifications Program.
8504240350 850422 PDR ADOCK 05000461 g
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h U- 0887 L30- 85 (04-22)-L 1A.120 Enclosures #2 and #3 to the LRG-II paper provided proposed Technical Specifications related to "Drywell Post-LOCA Vacuum Breakers" and "Drywell Air Locks".
IP's commitment to incorporate these into the CPS Technical Specifications remains unchanged.
The Drywell low pressure leakage testing frequency originally proposed in LRG-II paper 3-CSB (i.e., 40t 10 month intervals) was consistent with containment testing required of 10CFR50 Appendix J Type A tests. Compensatory local leak rate testing and/or visual examination of the Drywell penetration seals following maintenance was described.
Based on the test frequency, committed herein, IP no longer considers the compensatory local leak rate testing of the Drywell penetration seals necessary at CPS. As such, routine local leak rate tests will not be performed.
Finally,-as noted above. the September 30, 1983 IP submittal included the CPS-specific position on Drywell venting for pressure control. This position is identical to that previously approved by the i
NRC for Mississippi Power & Light's Grand Gulf Nuclear Station.
IP's position on this matter remains unchanged. The Staff's January 17, 1985 letter only addressed the LRG-II paper and thus did not confirm acceptance of this position. This position will be incorporated-into the CPS Technical Specifications.
Should you have any additional questions on this issue, please a
contact me.
Sincerel yours, l
Q '.
,6fA, h
F. A. Sp nge erg Directo-
- Nutlear Licensing i
and Configuration Nuclear Station Engineering TLR/ lab
'cc:
B. L. Siegel, NRC Clinton Licensing Project Manager NRC Resident Office Regional Administrator, Region III, USNRC Illinois Department of Nuclear Safety i
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