JSP-982-90, Revised Application for Amend to License NPF-62,correctly Identifying Operational Condition for Which Proposed Exception to Tech Spec 4.0.4 Applicable in Relation to Surveillance Requirements

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Revised Application for Amend to License NPF-62,correctly Identifying Operational Condition for Which Proposed Exception to Tech Spec 4.0.4 Applicable in Relation to Surveillance Requirements
ML20066A468
Person / Time
Site: Clinton Constellation icon.png
Issue date: 12/20/1990
From: Jamila Perry
ILLINOIS POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20066A470 List:
References
JSP-0982-90, JSP-982-90, U-601738, NUDOCS 9101030289
Download: ML20066A468 (2)
v • d • e


Text

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. CLINTON POWER STATION P.O. DOX 078. CLINToN, ILLINolS 61727 J. STEPHEN PERRY, Vier President (217) 935 6226 JSP-0982-90 December 20, 1990 10CFR50.90 Docket No. 50-461 Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Subject:

Clinton Power Station Proposed Amendment of Facility Operatina License No. NPP-62

Dear Sir:

By letter dated August 31, 1990 (reference U-601730),

Illinois Power (IP) applied for amendment of Facility operating License No. NPF-62, Appendix A - Technical Specifications, for Clinton Power Station (CPS). That request consisted of proposed changes to the neutron monitoring function requirements of Technical Specifications 3/4.3.1, " Reactor Protection System Instrumentation"; 3/4.3.6, " Control Rod Block Instrumentation";

and 3/4.3.7.6, " Source Range Monitors." Included in these proposed changes was a proposed statement of exception to the provisions of Technical Specification 4.0.4 for surveillance requirements pertaining to the source range monitor (and intermediate range monitor) functions under Technical Specification 3/4.3.6.

Subsequent to IP's submittal, it was identified that the applicable Operational Conditions for the noted proposed exception to the provisions of Technical Specification 4.0.4 did not precisely agree with the applicable Operational Conditions specified for the source range monitor function Surveillance Requirements. Therefore, this revision is being submitted to correctly identify the Operational Condition for which the proposed exception to Technical Specification 4.0.4 is applicable in relation to the surveillance requirements for the source range monitor functions under Technical Specification 3/4.3.6.

As identified in IP's August 31, 1990 request, the proposed exception to the provisions of Technical Specification 4.0.4 is only applicable during plant shutdowns following extended operation in Operational Condition 1 such that the required intermediate range monitor (IRM) and source range monitor (SRM) surveillances cannot be maintained current. (The IRMs and SRMs are not required to be operable in Operational Condition 1.)

During plant operation in Operational Condition 1, the IRMs and SRMs are withdrawn in order to prolong their life. Under these conditions, entry into Operational Condition 2 (reactor mode 9101030289 901220 dh POR ADOCK 05000461 i (I \

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switch in the.STARTUP/ HOT STANDBY position) is' required in order

'to perform the required IRM-Channel-Functional testing.

Therefore, IP proposed the exception to the provisions of Technical-Specification 4.0.4 for the IRM functions to allow entry into Operational Condition 2 under these conditions.

As' stated above, the SRMs are fully withdrawn during plant operation in Operational Condition 1. Entry into Operational Condition 2 during a controlled shutdown is typically performed at-approximately 10% reactor power. _This power level is above that which will_ result in an SRM Upscale trip. Therefore, the SRMs are not inserted into the reactor core until reactor power-has been reduced to the lower-ranges of the IRMs. Additionally, the SRMs are not required to be operable (per Technical Specification 3/4.3.7.6) until the IRMs are on range 2 or below.

Therefore, the proposed exception to the provisions of-Technical Specification 4.0.4 (and the associated 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> time limit) for the-SRMs should apply upon reaching " Operational Condition-2 with the IRMs on range 2 or below" versus " Operational Condition 2."

This revision is also consistent with the proposed exception to the provisions of Technical Specification 4.0.4 provided in IP's original request-for the SRM surveillance requirements of Technical Specification 3/4.3.7.6.

The justification for this revision is bounded by the original justification provided in IP's August 31, 1990 request. Further, the' Basis for No Significant Hazards Consideration and the basis for meeting the criteria given in 10CFR51.22 (c) (9) for a categorical exclusion from the requirement for an Environmental Impact Statement, as provided_in the original request, remain unchanged. A marked-up copy of the affected page (page 3/4 3-63) from the August 31, 1990 request is attached. (The requested revisions _to the August 31, 1990' request are identified by double change bars.) Additional pages from the August 31, 1990 request are also attached for information only Sincerely yours, s

a. S. . Porr Vice President DAS/alh-Attachment Dcc: Regional--Administrator, Region III, USNRC NRC Clinton Licensing Project Manager NRC Resident Office Illinois Department of Nuclear Safety i

a . - - ._ . - . - .- . . - - - - - -- .- - - - . .-

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