U-602192, Application for Amend to License NPF-62,changing Tech Specs 3.3.2, Instrumentation-Containment & Reactor Vessel Isolation Control Sys & 3.6.5, Drywell Post-LOCA Vacuum Relief Valves

Application for Amend to License NPF-62,changing Tech Specs 3.3.2, Instrumentation-Containment & Reactor Vessel Isolation Control Sys & 3.6.5, Drywell Post-LOCA Vacuum Relief Valves

ML20058K647
Person / Time
Site:	Clinton
Issue date:	12/10/1993
From:	Phares R ILLINOIS POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20058K656	List: ML20058K659 U-602192, Application for Amend to License NPF-62,changing Tech Specs 3.3.2, Instrumentation-Containment & Reactor Vessel Isolation Control Sys & 3.6.5, Drywell Post-LOCA Vacuum Relief Valves
References
U-602192, NUDOCS 9312150349
Download: ML20058K647 (2)

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. Ithnais Powm Company ,

Cknton Power Station PO Box 678 Chnbn. IL 61727 Tel 217 9354881 U-602192 1A7-93(1210)LP BE.100c December 10, 1993 j Docket No. 50-461 Document Control Desk Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Clinton Power Station Proposed Cha_nget.to Technical Spscification Bases

Dear Sir:

The purpose of this letter is to request changes to Illinois Power Company's Clinton Power Station (CPS) Technical Specification Bases. One of the proposed changes revises the value of a particular parameter that was re-evaluated as a result of a recently completed analysis to support relaxation of the required tolerance for the safety-mode lift setpoint for the safety / relief valves (SRVs).

The remaining two changes are associated with previously submitted proposed changes to Technical Specifications 3.3.2, " Instrumentation-Containment and Reactor Vessel Isolation Control System," and 3.6.5, "Drywell Post-LOCA Vacuum Relief Valves." ,

The Bases contained in the Clinton Power Station Technical Specifications summarize the reasons for the Specifications in Sections 2.0,3.0 and 4.0, but in accordance with 10CFR50.36, are not part of the Technical Specifications. Therefore, the proposed Bases changes submitted via this letter are not being submitted as an applicatiun for amendment of Operating License NPF-62 since the requirements of 10CFR50.90 are not applicable to such changes.

Each Bases change is discussed in detail in its own attachment to this letter. Marked-up/ revised Bases pages reflecting the proposed changes are also included in each respective attachment. ,

Sincerely yours, g . litA&

Richard F. Phares i Director-Licensing ,

TBFJnis Attachment cc: NRC Clinton Licensing Project Manager NRC Resident Office, V-690 Regional Administrator, Region 111, USNRC lilinois Department of Nuclear Safety

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, Attachment 1 l to U-602192 ,

Page1 of3- I Proposed Bases Changes for Technical Specification 3.3.2 i

By letter U-602070 dated December 15, 1992 lilinois Power (IP) submitted proposed changes to Clinton Power Station (CPS) Technical Specification 3.3.2, " Instrumentation-Containment and Reactor Vessel Isolation Control System" Subsequent to that submittal, and based on discussions with NRC ,

staff personnel involved in the review and approval of the proposed Technical Specification changes, it was determined that IP should submit proposed changes to the associated Bases. Bases changes are hereby requested as further discussed below.

The changes proposed for CPS Technical Specification 3.3.2 were requested primarily to permit a .

longer out-of-service time for an inoperable leak detection difTerential temperature instrument  ;

channel (s) when a sufficient number of associated ambient temperature instrument channels are ,

operable. As noted in IP's December 15, 1992 submittal, the proposed changes to the associated Technical Specification Action Statement (s) would permit a loss of diversity for mitigating the effects of a steam leak in the associated area (s) for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. However, this loss of diversity [i.e., having a I differential temperature instmment channel (s) inoperable] would be permitted only if a sufficient number of ambient tentperature instrument channels are operable. No loss of function would therefore be permitted, thus ensuring that an automatic isolation in response to a steam leak is still capable of -

occurring.

Discussions with NRC staff personnel have determined that it would be appropriate for IP to propose a change to the corresponding BASES for Technical Specification 3.3.2 addressing the extended allowed ,

out-of-senice time for the differential temperature instrumentation. Under the proposed change, the ,

Bases would note the extended time is pennitted on the basis that no loss of function exists during the time that the differential temperature instrument channel (s) is (are) inoperable. Accordingly, proposed ,

changes to the Bases for Technical Specification 3 '4.3.2 are proposed as indicated on the following l

pages (pages 2 and 3 of this attachment). The additional text should be inserted as shown.

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Note '

It should be noted that the proposed Technical Specification changes described above (submitted via IP letter U-602070 identified above) were recently approved by the NRC and issued via Amendment No.  !

85 to the CPS Operating License. Although the NRC letter and Safety Evaluation accompanying the i amendment did not discuss proposed changes to the Bases associated with Technical Specification 3.3.2, IP is submitting proposed changes to the Bases (as described above) notwithstanding.

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