ML20035B134
| ML20035B134 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/23/1993 |
| From: | Schrage J COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| GL-86-10, GL-88-12, NUDOCS 9303310187 | |
| Download: ML20035B134 (2) | |
Text
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Downers Grove, lilinois 60515 March 23,1993 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Quad Cities Station Units 1 and 2 Additional Information Pertaining to Proposed Technical Specification Amendment i
NRC Docket Nos. 50-254 and 50-265
References:
(a)
J.L. Schrage to T.E. Murley letter dated September 30,1991.
(b)
J.L. Schrage to T.E. Murley letter dated October 2,1991.
t (c)
Meeting between CECO (J. Schrage) and the NRC (C. Patel) on February 17,1993.
(d)
T.J. Rausch to D.G. Eisenhut letter dated July 1,1982.
l (e)
D.B. Vassallo to L. DelGeorge. letter dated December 30, 1982.
l Dr. Murley:
In References (a) and (b), Commonwealth Edison Company (CECO) submitted a
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proposed Technical Specfication (TS) amendment to Facility Operating Licenses DPR-29 and DPR-30 (Quad Cities Station Units 1 and 2). The proposed amendment implemented the guidance of Generic Letters (GLs) 86-10 and 88-12, by replacing the current license condition regarding fire protection with a new standard license condition, and deleting existing TS Section 3.12/4.12, " Fire Protection Systems". During the Reference (c) l teleconference, the NRC indicated that in order to fully implement GLs 86-10 and 88-12, i
CECO would be required to submit proposed Technical Specifications for the Alternate Safe -
I Shutdown Equipment (consistent with the guidance in GL 81-12, Enclosure 1, item 8j).
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9303310187 930323 1
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Ifr[Murley March 23,1993 I
t CECO provided a response to GL 81-12, Enclosure 1, item 8j in Reference (d). This l
response stated.
"While Technical Specifications should call out the surveillance requirements l
1 and intervals, they should not address actions to be taken to carry out those i
requirements. The best method for describing how a Technical j
Specification requirement is fulfilled is by Station procedures. Station l
Procedures have the flexibility of being upgraded for the best methods of doing surveillance testing in a timely manner. Tech Specs require substantial time for upgrading as improvements in methods of surveillance testing are j
found."
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t The NRC cited Reference (d) in the Quad Cities Station Safety Evaluation for Appendix R (Reference (e)). In addition, the NRC stated that CECO "should propose i
Technical Specifications for the new Safe Shutdown Makeup pump comparable to those currently in place for the Reactor Core Isolation Cooling system."
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Based upon the Reference (c) discussions, and the Quad Cities Station Safety a
Evaluation for Appendix R (Reference (e)), CECO will submit a proposed Technical i
Specification for the Safe Shutdown Makeup Pump (SSDMP) as part of the current i
Technical Specification Upgrade program. This proposed specification will be based upon -
the current administrative controls and surveillance requirements for the SSDMP which are 4
described in the Quad Cities Safe Shutdown Analysis.
If there are any questions or comments, please direct them to John L. Schrage at i
708-663-7283.
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t-i Sincerely,
,/
j
/ / John 16 Schrage
(/ Nuclear Licensing Administrator t
i cc:
A. Bert Davis, Regional Adtninistrator - Rill C.P. Patel, Project Manager - NRR T.E. Taylor, Senior Resident inspector - Quad Cities Office of Nuclear Safety -IDNS
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