ML20094A887

Application for Amend to Licenses NPF-11 & NPF-18,changing Tech Specs Re Accident Monitoring Instrumentation (NUREG-0737,Items II.F.1.1,II.F.1.3 & II.F.1.6).Fee Encl

ML20094A887
Person / Time
Site:	LaSalle
Issue date:	07/25/1984
From:	John Marshall COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20094A890	List: ML20094A887 ML20094A906
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM 9010N, GL-83-36, NUDOCS 8408060145
Download: ML20094A887 (4)

Text

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s Commonwe:lth Edison

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g O j AdJress Reply to. Post Office Box 767 4

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July 25, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

LaSalle County Station Units 1 and 2 Proposed Amendment to Technical Specification for Facility Operating License NPF-ll and NPF-18 Concerning Accident Monitoring Instrumentation NRC Docket Nos. 50-373 and 50-374 References (a): Technical Specification 3.3.7.5 (pages 3/4 3-69 and 3/4 3-70).

(b): Generic Letter 83-36, dated November 1, 1984. NUREG-0737 Technical Specifications.

(c): FSAR Section L. 30 Accident Monitoring Instrumentation.

(d): SER II.F.1 Attachment 1 (pages 23-71 through 23-77), Attachment 3 (pages 22-82 through 22-84) and Attachment 6 (page 22-87).

(e): SSER No. 2 II.F.1 (page 22-9).

Dear Mr. Denton:

Pursuant to 10 CFR 50.59, Commonwealth Edison proposes to amend

' Appendix A, Technical Specification, to Facility Operating Licenses NPF-11

'and NPF-18. These amendment changes are being submitted for your staff's review and approval.

The proposed change is enclosed in Attachment 2. The attached change has received both On-Site and Of f-Site review and approval. We have reviewed this amendment request and find that no significant hazards consideration exists. Our review is documented in Attachment 3.

Commonwealth Edison is notifying the State of Illinois of our request for this amendment by transmitting a copy of this letter and its attachments to the designated State Official.

N fjhfo gh @

H.R. Denton July 25, 1984 In accordance with 10 CFR 170, a fee remittance of $150.00 is enclosed.

Please direct any questions you may have concerning this matter

-to this office, t Three (3) signed originals and thirty-seven (37) copies of this

-transmittal and its attachments are provided for your use.

Very truly yours, W

J. G. Marshall Nuclear Licensing Administrator Attachments (1): Background (2): Technical Specification Change to NPF-18 (3): Evaluation of Significant Hazards Consideration cc: Region III Inspector - LaSalle A. Bournia - NRR G. Wright - Ill.

SUBSCRIBED and SWORN to before me this c95tiday of .h , 1984 pas a 0-Notary Public 9010N'

ATTACHMENT 1 l'

LASALLE COUNTY STATION UNITS 1 AND 2 TECHNICAL SPECIFICATION CHANGE REQUEST BACKGROUND: The LaSalle County Station Unit 1 and Unit 2 Technical Specifications (Appendix A to Licenses NPF-ll and NPF-18) contain Accident Monitoring Instrumentation Limiting Conditions for Operation for Noble Gas Ef fluent Monitors (II.F.1.1), Containment High-Range Radiation Monitors (II.F.1.3) and Containment Hydrogen Monitor (II.F.1.6) as required by reference b).

During the review of reference b) it was noted that the present LaSalle County Station Technical Specifications (reference a) were more limiting than those proposed in Enclosure 3 of Reference b). The changes to LaSalle County Units 1 and 2 Technical Specification 3.3.7.5 as indicated on Attachment A reflect the model Technical Specifications of reference b)

DISCUSSION:

LaSalle County's compliance with NUREG-0737 for items II.F.1.1, II.F.1.3 and II.F.1.6 are discussed in references c), d), e). As stated in reference b) the Technical Specifications should be revised for the following reasons:

II.F.1.1: Noble Gas effluent monitors provide information, during aid following an accident, which are considered helpful to the operator in accessing the plant condition. It is desired that these monitors be operable at all times during plant operation, but they are not required for safe shutdown of the plant. In case of failure of the monitor, appropriate actions should be taken to restore its operational capability in a reasonable period of time. Considering the importance of the availability of the equipment and possible delays involved in administrative controls, 7 days is considered to be the appropriate time period to restore the operability of the monitor. An alternate method for monitoring the ef fluent should be inititiated as soon as practical, but no later than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the identification of the failure of the monitor. If the monitor is not restored to operable condition within 7 days after the failure, a special report should be submitted to the NRC within 14 days following the event, outlining the cause of inoperability, aitions taken and the planned schedule for restoring the system to operable status.

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II.F.1.3 A minimum of two in containment ladiation-level monitors with a maximum range of 10 8 rad /hr (107r/hr for photon only) should be operable at all times except for cold shutdown and refueling outages. In case of failure of the

' monitor, appropriate actions should be taken to restore its operational capability as soon as possible. If the monitor is not restored to operable condition within 7 days after the_ failure, a special report should be submitted to the NRC within 14 days following the event, outli.ning the cause of inoperability, actions taken and the planned schedule for restoring the equipment to operable status.

II.F.1.6- The containment hydrogen concentraticn analyzers monitor the primary containment gas for hydrogen. These monitors are normally in standby and initiate on reactor water level low (level 2), or high drywell pressure. The primary containment at LaSalle County Station is inerted with nitrogen per Technical Specification and has 2 redundant hydrogen recombiners (Technical Specification 3.6.6.1)

Since the inoperability of the hydrogen monitors is lesser concern.than other accident monitoring instrumentation due Printout cancelled by operator.