ML20234D141
| ML20234D141 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 12/28/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-1002 3863K, NUDOCS 8801060466 | |
| Download: ML20234D141 (2) | |
Text
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P c A) G.e FirsWarional Plaza,6hicago, Illirvis Commonwealth Edison
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- Address RIply to: Post Off ce Sox 767 Chicago, Illinoia 60690l 0767-December 28, 1987 s
Mr. Thomas E. Murley, Director Office of Nuclear Reactor Oegulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk
Subject:
Praidwood Station Units 1 and 2 Safety Evaluation Report NRC Docket Nos. "iG-451 and'50-457 s
References (a): NUREG-1002,. Safety Evaluation Report, Supplement #1, dated September,'1986 (b): NUREG-1002, Safety Evaluation _ Report, Supplement #2, dated October, 1986 (c): NUREG-1002, Safety Evaluation Report.
Supplement #3, dated May, 1987 (d): NUREG-1002, Sat'ety Evaluation Report, supplement #4, dated July, 1987
Dear Mr. Murley:
References (a), (b), (c), and (d) provided the NRC' review and-evaluation of various commonwealth Edison submittals. Commonwealth Edison has reviewed these documents and is providing the following comments:
(1) Reference (a), Section 4.4.7.2.1, page 4-5, entitled "Subcooled
- 1 Margin Monitor". This section makes refer d e.to a containment
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radiation greater than 10 R/hr. This value should be 20 Jt/hr, as used in the Braidwood Emergency Operating procedures; and as supported by Byron /Braidwood FSAR Section E-30, pages E30.2 and E30.3.
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(2) Reference (b), Section 6.5.1, page 6-7, entitled'" Engineered Safety 1
Feature (ESP) Atmospheric Cleanup System". This section makes' reference to the upper cable spreading room being required to be
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maintcined at a positive pressure of 0.125 inch Water Gauge at the-time of Braidwood Unit 2 operation. Per Technical Specification:
I 4.7.6.e<5'), page 3/4 7-15; and Byrco/Erafdwood FSAR section 6.4.2.3, page 6.4-3, this pressure value should be 0.02, inches, Water Gauge.
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'T.E. Murley December 28, 1987 (3) Reference (c), Section 9.5.1.2, page 9-1, entitled " Fire Protection Program Requirements". This section makes reference to our letter dated August 29, 1986 and states that we committed to incorporate a proposed FSAR revision to Section 9.5-1 into a future PSAR amendment.
In actuality, the August 29, 1986 letter provided the following statement in this regard:
.... the Byron /Braidwood Station Final Safety Analysis Report (FSAR), Section 9.5.1 currently includes by reference to the Fire Protection Report the fire protection program and major commitments, including the fire hazard analysis.
Therefore no additional FSAR changes should be required." Via this approach, amendments to the Byron /Braidwood Fire Protection Program provide an appropriate means to update the Byron /Braidwood FSAR in this area. Currently, Amendment 10 dated June, 1987, to the Byron /Braidwood Fire protection Report has been
'aubmitted to the NRC.
(4) Reference (G), Section 18.3, page 18-2 entitled "Fafety. Parameter Display System (SPDS)".
This section states that in our letter, dated October 10, 1986, that we committed to submit the Verification / Validation (V/V) report for Braidrod Station for the SPDS by August 1, 1987.
In actuality, our October 10, 1986 letter commits to providing the V/V report to the NRC prior to startup t'ollowing the first refueling outage for Braidwood Unit 1.
These items have been discussed with members of the NRC Staff and are being provided to you for information and use. Please direct any questions concerning any of these matters to this office.
Very truly yours,
.b. f w = -
S. C. Hunsader l
Nuclear Licensing Administrator i
cc:
S. Sands NRC RIII Braidwood Resident Inspector
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l 3863K
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