ML20086A609
| ML20086A609 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/13/1991 |
| From: | Schrage J COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9111190257 | |
| Download: ML20086A609 (3) | |
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Ctmmonwealth Edison C >
1400 Opus Place i
Downers Grove, Illinois 60515 November 13,1991 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 Nuclear Power Station Units 1 and 2 Supplement to Application for Amendment to Facility Operating Licenses DPR-29 and DPR-30, Appendix A, Technical S cifications Technical Specification pgrade Progmm NBC_DocheLNocJ0 254And_50 265
Reference:
R. Stols to T.E. Murley letter dated Septem~ er 17,1991 Dr. Murley:
In 1990, Quad Cities Statlon initiated i. e Tlal program to enhance the Station's performanco in various aspects of plant operatic.:. ine Performance Enhancement Program
. (PEP) was developed by atsessing esating improvement plans, identifying potential weaknesses and prioritizing improvement actions. Necessary i provements to the Technical Specifications were identified as one of the Station's top priori ssues. The Technical Specification Upgrade Program was subsequently initiated an has been previously discussed -
with members of the NRR staff.
The referenced letter transmitted a proposed amendment to Section 3.3/4.3
" Reactivity Control' as part of the Technical Specification Upgrade Program. Commonwealth
. Edison has identified an inadvertent omission of information with respect to the " Description of Changes" section and CECO's evaluation pursuant to 10 CFR 50.92(c).
The " Description of Changes" section, Item 12. " Control Rod Scram Accumulators"
~
, -contained an incomplete sentence at the end of the section. The last sentence of this item
- description should read as follows
Proposed SR 4.3.G added from STS guidelines requires at least once per 7 days that the pressure for each control rod scram accumulator be verified to be 2 950 pslg, unless the control rod is inserted and disarmed or scrammed.
' The " Basis for No Significant Hazards Consideration" section of the referenced application did not contain an evaluation of the proposed changes to the Control Rod Drive Housing Support Specifications, Please find the missing information attached in the Enclosure. This should be inserted as Subsection 1) p. of Section 6. "Significant Hazards Considerations.
The missing information was unintentionally omitted from the original referenced submittal. Commonwealth Edison regrets any inconvenience that this may have caused.
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Dr. Thomas E. Murley Novemt'ar 13,1991 A
To the best of my knowledge and belief, the statements contained are true and correct. In some respects, these statements are not based on my personal knowledge but obtained information furnished by other Commonwealth Edison emoloyees and consultants.
Such Information has been reviewed in accordance with Company practice and I believe it to be reliable.
Commonwealth Edison is notifying the State of lilinois of this Supplement to the application for amendment by transmitt!ng a copy of this letter and its attachment to the designated State Official.
If there are any comments or questions on this information please ditect them to John L. Schrage at 708 515-7283.
Respectfully, John L.
chrage Nuclear Licensing Administrator
Enclosure:
Evaluation for Significant Hazards Consideration Supplement
- cc:
A. Bert Davis, Regional Administrator - Rlli L.N. Olshan, NRR Project Manager - Quad Cities T.E. Taylor, Senior Resident inspector - Quad Cities Illinois Department of Nuclear Safety l
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ENCLOSURE EVALUATION FOR SIGNIFICANT HAZARDS CONSIDERATION SUPPLEMENT
- 1) p.
Proposed Changes to the Control Rod Drive Housing Supports The proposed Specification 3.3.J/4.3.J for the Control Rod Drive Housing Supports is based on present requirements and rewritten to STS guidelines. The control rod drive housing supports are required to be in place in Operational Modes 1,2, and 3.
The proposed LGo and Applicability follow STS guidelines and implement present technical specification provisions. Present provisions require the control rod drive housing support to be in place during reactor ower operation and when the reactor coolant system is pressurized above atmo ric pressure with fuelin the vessel, unless all centrol rods are fully Inserted an the Shutdown Margin provisions are met. The proposed applicability of Operational Modes 1,2, and 3 cover the reactor conditions of power operation and when the reactor coolant system can be pressurized. The present Specifications do not contain Action steps when the Control Rod Drive Housing Supports are not in place in the applicable Operadonal Modes.' The proposed Action follows STS guidelinec and is intended to avoid the use of Specification 3.0.A by requiring the reactor to be in at least Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The present Surveillance Requirement for the control rod drive housing supports 4.3.B.2 is retained in oposed SR 4.3.J and rewritten using STS wording. The present level of operabili for the Control Rod Drive Hcusing Supports are rnalntained by the proposed c anges and more explicit details are provided using STG wording and guidelines. Therefoie, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
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