ML20137H571
| ML20137H571 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/27/1997 |
| From: | Kraft E COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ESK-97-073, ESK-97-73, NUDOCS 9704020281 | |
| Download: ML20137H571 (3) | |
Text
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Commonwealth Illison Ormpany Quad Citics Generating Station 22710 206th Avenue North r
Cordova, 11,61242-9740 Tel 309m22 4 i ESK-97-073 March 27,1997 United States Nuclear Regulatory Commission Washington, D. C. 20555-0001 Attention:
Document Control Desk
Subject:
Quad Cities Nuclear Power Station Units 1 and 2 Supplement to Emergency Application for Amendment to Facility Operating Licenses DPR-29 and DPR-30 Pursuant To 10CFR50.91(a)(5)
Discrepancy in UFSAR Value for Secondary Containment Free Volume Docket Nos. 50-254 and 50-265
Reference:
(a)
E. S. Kraft letter to USNRC dated March 26,1997, concerning Discrepancy in FSAR Value for Secondary Containment Free Volume.
The purpose of this supplemental response is to clarify Comed's evaluation of the basis for satisfying the criteria of 10CFR50.91(a)(5). On March 26,1997, Reference (a) was submitted to the NRC staff, requesting approval on an emergency basis, pursuant to 10CFR50.91(a)(5), of a change to the Technical Specifications concerning Standby Gas Treatment charcoal efliciency, and the free volume of the Secondary Containment. This letter supplements the information provided in the " Basis for Emergency Amendment" section of Attachment A of Reference (a).
On March 24,1997, Comed determined that a potential Unreviewed Safety Question may exist concerning a discrepancy in the UFSAR value for Secondary Containment free volume. This discrepancy results in a calculated increase in dose to the operators in the Control Room during an accident. A Safety Evaluation in accordance with 10CFR50.59 was initiated, and an emergency Technical. Specification change was drafted to decrease the methyl iodide penetration for SBGT charcoal allowed by the Technical Specifications. On March 26,1997, Comed completed the Safety Evaluation, determining that an Unreviewed Safety Question existed due to a reduction in the margin to safety and an increase in the consequences of an accident.
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r ESK-97-073 USNRC 2
March 27,1997 Pursuant to 10CFR50.9)(a)(5), Comed requests emergency approval of this amendment to address the Unreviewed Safety Question and to approve a decrease in the methyl iodide penetration for SBGT charcoal allowed by the Technical Specifications.
Approval of this amendment on an emergency basis is warranted because the current situation satisfies the Commission's defmition of emergency: Failure to act in a timely way would result in the prevention of resumption of operation [10CFR50.91(a)(5)].
Quad Cities had been operating in its current configuration on the basis of an operability determination which demonstrated that the standby gas treatment system was capable of performing its intended safety function. Operation was planned to continue untd approval of the design basis reconstitution of the Control Room dose calculations
. (submittal planned for April 15, 1997). However, during the current forced outage, based upon lessons learned from other Comed plants and further self-assessment, Quad Cities reexamined earlier evaluations and concluded that an Unreviewed Safety Question existed for the standby gas treatment system. On March 24,1997 it was determined that an Unreviewed Safety Question may exist. Prior to that time, no Unreviewed Safety Question was anticipated. Therefore, this situation could not have been avoided by Quad Cities.
Quad Cities Unit 1 is currently ready to return to service afler completion of activities from a forced outage. Per the discussion presented above and in Reference (a), this emergency situation could not have been avoided and therefore, Comed believes that the circumstances described above meet the criteria of 10CFR50.91(a)(5) for review and approval on an emergency basis.
The supplemental information presented herein is administrative in ne'. e and serves to expand the basis for satisfying the criteria specified in 10CFR50.91(a)(5). The information presented in Reference (a) continues to demonstrate that the proposed Technical Specification change is acceptable for Quad Cities Station. Comed's significant hazards evaluation presented in Reference (a) is unaffected by the supplemental information presented herein as the ptoposed amendment continues to ensure that operation of the facility in accordance with the proposed Technical Specification changes do not involve a significant increase in the probability or consequences of any accident previously evaluated; or create the possibility of a new or different kind of accident from any accident previously evaluated; or involve a significant reduction in a margin of safety. As such, a revised significant hazards evaluation is I
unwarranted.
To the best of my knowledge and belief, the statements contained above are true and correct. In some respect these statements are not based on my personal knowledge, but obtained information furnished by other Comed employees, contractor employees, and consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable.
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t ESK-97-073 USNRC 3
March 27,1997 Comed is notifying the State ofIllinois of this application for amendment by transmitting l
a copy of this letter and its attachments to the designated state official.
If you have any questions concerning this letter, please contact Charles Peterson, Regulatory AfTairs hianager, at (309) 654-2241, extension 3609.
Respectfully, 08 Y (1 E. S. Kraft, J/
Site Vice President Quad Cities Station Subscribed and Sworn to before me on this l'7 day of
" OFFICIAL SEAL"
// nae //
, 1997.
UNDAt.EE STOEMM!R NotwyPutte.3Me of Encis
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N'otary Pub'lic cc:
A. B. Beach, Regional Administrator, Region III R. hl. Pulsifer, Project hianager, NRR C. G. hiiller, Senior Resident Inspector, Quad Cities W. D. Leech, hiidAmerican Energy Company D. C. Tubbs, hiidAmerican Energy Company F. A. Spangenberg, Regulatory Affairs hianager, Dresden P. L. Piet, Nuclear Licensing INPO Records Center Office of Nuclear Facility Safety, IDNS DCD License (both electronic and hard copies) l l
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