ML20235U251

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Provides Advance Notification of Changes to Be Made to Plants Fsar.Affected Page 14.2-57 & Basis for Change Encl
ML20235U251
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 07/15/1987
From: Hunsader S
COMMONWEALTH EDISON CO.
To: Murley T
Office of Nuclear Reactor Regulation
References
3350K, NUDOCS 8707220409
Download: ML20235U251 (3)


Text

Comm:nwealth Edison k " ! One First National Plaza. Chicago, Illinois i

/ Address Riply to: Post Office Box 767

\\/ Chicago, Illinois 60690 - 0767 July 15, 1987 Mr. Thomas E. Murley, Director office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Final Safety Analysis Report Revisions NRC Docket Nos. 50-454/455 and 50-456/457

Dear Mr. Murley:

This letter provides an advance notification of changes to be made to the Byron /Braidwood FSAR that are to be included in a future FSAR Amendment submittal.

Attachment A includes the affected Byron /Braidwood FSAR page 14.2-57 with the indicated changes so marked.

Attachment B provides the basis for making this change. The indicated changes more correctly represent the Byron /Braidwood design and Technical Specifications.

This advance copy is being provided to allow for early NRC review.

? lease address any questions concerning this matter to this office.

Very truly yours, S. C. Hunsader Nuclear Licensing Administrator Attachment Cs cc:

L. Olshan J. Stevens Byron Resident Inspector Braidwood Resident Inspector 3350K B707220409 870715 PDR ADOCA 050 4

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B/B-FSAR AMENDMENT.40 NOVEMBER 1982

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A TABLE 14.2-45 REACTOR COOLANT ISOLATION VALVES (Preoperational Test)

Plant Condition or Prerequisite Prior to core loadings pric: tc and during integrated hot functional testing with the RCS at various temperatures

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and pressures.

(y q p; Test Objective de+ce mine. +he c9enin3 a nd clo3' "O 4 '* CJ l

To _,;.;;.;t: t; ;;;::ticrMof the main coolant isolation valves durin3 y -and associated alarms, indications, and interlocks.

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lo S c +ca +- of +he.

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To per -Form a Test Summary in+cei ock.5 To vers'h The controligand indications for each isolation valve.

.will he Sm.uu m ow0.

Each valve will be verified to cycle.

""A 2C cci;ted suLu lesh; ;;;ifica t cp;;;t-c.

Acceptance Criteria The main coolant isolation valves and interlocks operate in accordance with Subsection 7.6.8.

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14.2-57

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i ATTACHMENT B Table 14.2-45 is being revised based on the following:

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1) Bryon/Braidwood Table 14.2-45 was drafted based on N-1 (3-loop) operation and Byron and Braidwood stations are not licensed for N-1 operation.

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2) Per the Byron /Braidwood Tech. Spec. page 3/4 4.7, Section 3.4.1.5.1:

i All RCS loop isolation valves (hot leg and cold leg stop valves) shall be open and power removed from the isolation valve operators.

Applicability: Modes 1,2,3, and 4.

Action: With any RCS loop isolation valve closed, suspend startup of the isolated loop and be in HOT SHUTDOWN within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

3) Per Byron /Braidwood FSAR Section 15.4.4.1, timed bypass flow is not applicable in Modes 5 and 6.
4) Proper operation of the loop stops, bypass valves, associated alarms and interlocks will be functionally tested by commonwealth Edison as a System Demonstration test.

3350K

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