ML20009E199
| ML20009E199 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/20/1981 |
| From: | Rausch T COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20009E200 | List: |
| References | |
| 2309N, NUDOCS 8107270222 | |
| Download: ML20009E199 (2) | |
Text
[C'N Commonwealth Edison
) One First National Plaza. Chic %go. Illinois p
( C/ ' Address Reply to: Post Office Box 767
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Chicago, Illinois 60690 e-ao S D (fb S
'e July 20, 1981 V 4r C
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Mr. Harold R.
Denton, Director (p-g$v
- 11 Office of Nuclear Reactor Regulation
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sf U.S. Nuclear Regulatory Commission
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Washington, DC 20555
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ps
Subject:
Quad Cities Station Units 1 and 2 Supplement to Proposed Amendment to Facility Operating Licenses DPR-29 and DPR-30 Regarding Inservice Inspection (ISI)
NRC Docket Nos. 50-254 and 50-265-References (a):
R. F. Janecek letter to Director of NRR dated Septer:ber 30, 1980 (b):
C. Reed letter to Director of NRR dated April 18, 1979
Dear Mr. Denton:
In Reference (b), Commonwealth Edison proposed to amend Quad Cities Units 1 and 2 Technical Specifications in order to conform with the ASME Boiler and Predsure Vessel Code Section XI l
requirements so that no conflicts ex st between the two documents.
Also proposed were changes which eliminate the testing of redundant components when the related subsystems are determined to be inoperable.
The purpose of this transmittal is to revise the Reference (b) amendment request to include two additional changes.
Attachment I contains the aoditior.al Technical Specification changes for Quad Cities Unit 1 and Attachment 2 contains the Quad Cities Unit 2 changes.
These proposed changes have received On-Site and Off-Site review and approval and are discussed below.
Page 3.7/4.7-5 and 16 geS 5
The Pressure Suppression Chamber-Dryrell Vacuum Breakers, ffl even though not in an ASME Section XI referenced system, were l
required by the NRC (in June, 1930 NRC/ CECO. working sessions at Quad Cities Station) to be included in the In-Service Testing (ISI) program.
Revision 1 to the Quad Cities ISI program, dated 9/24/80 and transmitted in Reference (a) reflects this requirement.
The rules of the ASME code were applied, and an exercising test l
0107270222 810720 PDR nDOCK 05000254 l
P PDR k
. frequency of every 90 days (quarterly) is required.
The Technical Specification surveillance requirements and bases have been revised to reflect this frequency.
Page 3.9/4.9-4 and 5 Reference (b) proposed changes to section 3.9.E.1 deleting the requirement to demonstrate the diesel-generator operability when another diesel-generator becomes inoperable.
The next paragraph (3.9.E.2) should have been revised at this time, but was not.
This-change rectifies that situation and also addresses this philosophy in the Bases.
Please direct any questions concerning these supplementary changes to this office.
Inree (3) signed originals and thirty-seven (37) copies of this transmittal are provided for your use.
Very truly yours, kl-/Aad Thomas J. Rausch Nuclear Licensing Administrator Boiling Water Reactors Attachments l
cc:
RIII Inspector - Quad Cities SUBSCRIBED and SWORN to j
before me hi
<@/ M day of-1981 Al k 0-tM Notary Pubiic l
2309N.
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