ML20098A979

Application for Amends to Licenses NPF-11 & NPF-18,revising Tech Specs Re Reactor Water Cleanup Pump Room High Ambient & High Differential Temp Isolation.Nshc Encl.Fee Paid

ML20098A979
Person / Time
Site:	LaSalle
Issue date:	09/19/1984
From:	John Marshall COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20098A985	List: ML20098A979 ML20098A986
References
9206N, NUDOCS 8409250344
Download: ML20098A979 (2)

Text

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/ N Commonwealth ECson

/ One First N;tional Plaza. Chicago, ilhnors l

( T Addr:ss Reply to: Post Office Box 767

\ j } Chicago. (Hinois 60690 September 19, 1984 Mr. Harold'R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear. Regulatory Commission Washington,-OC 20555 Sub ject: LaSalle County Station Units 1 and 2 Proposed Amendment to Technical Specification for Facility Operating License NPF-ll and NPF-18 Concerning Reactor Water Cleanup Pump Room High Ambient and High Differential Temperature Isolation NRC Docket Nos. 50-373 and 50-374 References (1): P& ids M-93 sheets 1 and 2, M-97 sheet 1 (Unit 1) and M-139 sheets 1 and 2, M-143 sheet 1 (Unit 2).

(2): UFSAR Table 7.3.2 (3): Technical Specification Tables 3.3.2-1, 3.3.2-2, 3.32-3, and 4.3.2.1-1.

(4): UFSAR Table 5.2.8 (5): GE Design Specification 22A2870.

(6): UFSAR Section 7.6.1.2.6.

Dear Mr. Denton:

Pursuant to 10 CFR 50.59,. Commonwealth Edison proposes to amend Appendix A, Technical Specification, to Facility Operating Licenses NPF-ll

-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-Off-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.

8409250344 840919 PDR ADOCK 05000373 '

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'H.:R. Denton September 19, 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.

Three (3) signed originals and thirty-seven (37)' copies of this transmittal and its attachments are provided for your use.

Very truly yours,

} A *1 Y J. G. Marshall Nuclear, Licensing Administrator

-1m Attachments (1): Background and Discussion (2): Technical Specification Change.to NPF-ll and NPF-18

.(3): Evaluation of Significant Hazards Consideration cc: Region III Inspector - LaSalle A. Bournia - NRR G. Wright - Ill.

SUBSCRIBED and SWORN to

, ibeforp me this / M day

-of dLhrtw_lAto ,1984 d{ cc- r tw Notary Public 9206N

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ATTACHMENT 1 LASALLE COUNTY STATION UNITS 1 AND 2 TECHNICAL SPECIFICATION CHANGE REQUEST BACKGROUND: The Reactor Water Cleanup System (RWCU) is normally in operation to maintain reactor water chemistry within required limits and is connected to the Reactor Coolant Pressure Boundary. The system outboard of the primary containment isolation valves is not however part of the reactor coolant pressure boundary. The system inlet side comes from the reactor vessel and/or the reactor recircula-tion pump suction lines through the primary containment.

The system returns to the feedwater line outside primary containment (See reference 1). The original design of the RWCU system was such that the RWCU system recirculation pumps contained reactor water at full operating temperataure and pressure. This water was cooled downstream with heat exchangers to below 1300F prior to entering the deminerali-zers. To allow for better pump operation based on operating experienceatotherplants,thesystemdesignwashhangedto move the RWCU pumps to a point in the system after the heat exchan water.gers to allow Based on the the pumps original to contain RWCU System lower temperature design, the pump room leak detection system was designed for hot teactor water which included the following: (1) system high differential flow, (2) RWCU pump rooms (3 rooms) high ambient and high differential temperature, and (3) reactor building sump high level. Items (1) and (2) above provide automatic isolation signals to the RWCU System and item (3) provides remote alarm provisions to the control room to allow the

( operator to manually isolate the RWCU system. These methods are summarized in reference (4). After the RWCU system configuration change, the RWCU pumps contained low temperature water and the ambient and differential tempereture monitors were no longer required (references 4 and 5). However the automatic isolation provisions based on temperature were not removed from the design and are installed in the plant and included in the Technical Specifications (reference 3). The cold portion of the RWCU system has differential flow as well as reactor low water level (level 2) automatic isolations. The system can also be isolated manually if area sump levels or other methods indicate leakage in the system (reference 6).

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' DISCUSSION:. Since'the ambient and differential temperature sensors are

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ineffective for detecting leakage of the cold water in the RWCU pump: room portion of the piping system, they should be removed from reference (3). At the present time the setpoints for these instruments are set to detect the equivalent leakage limit and are very near the normal operating conditions due to the lower temperature. This has caused unnecessary spurious isolations and several LERs when "no leaks were present. Sufficient diversity remains to ensure that actual leakage in the RWCU pump rooms is monitored and will be promptly isolated.

. Revisions to the UFSAR will be included in the next update.

Marked up Technical Specification pages which reflect this change are included in Attachment A.

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ATTACHMENT 3 i

SIGNIFICANT HAZARDS CONSIDERATION Commonwealth Edison has evaluated the proposed Technical Specification Amendment and determined that it does not represent a significant hazards consideration. Based on the criteria for defining a significant hazards consideration extablished in 10CFR50.92, operation of LaSalle County Station Units 1 and 2 in accordance with the proposed amendment will not:

'l) Involve a significant increase in the probability or consequences of an accident previously evaluated because the Reactor Water Cleanup (RWCU) System will still have adequate isolation capability and meets the requirements for cold system piping as specified in the FSAR for this system. This change updates the Technical Specifications to reflect the actual design of the RWCU system in that the RWCU recirculation pumps are presently located in a cold portion of the system.

2) Create the possibility of a new or different kind of accident from any accident previously evaluated because leakage from the RWCU System has already been evaluated.

3) Involve a significant reduction in the margin of safety because the reactor water cleanup system will still be monitored for leakage and will still isolate if the leakage exceeds the required limits. This change deletes only the temperature monitoring of the colder portions of the RWCU System where this type of monitoring is not very effective'and causes unnecessary isolations.

Based on the preceding discussion, it is concluded that the proposed system change clearly falls within all acceptable criteria with respect to the system or component, the consequences of previously evaluated accidents will not be increased and the margin of safety will not be decreased. Therefore, based on the guidance provided in the Federal Register and the criteria established in 10CFR50.92(e), the proposed change does not constitute a significant hazards consideration.

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