ULNRC-03681, Forwards marked-up Replacement Page 5 of Attachment 1 to & Two Replacement Page mark-ups for Insert 3/4 3-25 of Attachment 3 to
| ML20199B411 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 11/10/1997 |
| From: | Passwater A UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20199B415 | List: |
| References | |
| ULNRC-03681, ULNRC-3681, NUDOCS 9711180317 | |
| Download: ML20199B411 (3) | |
Text
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November 10, 1997 Umo Euum&v
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U.S. Nuclear Regulatory Commission
'd Attn: Document Control Desk Mail Station PI-137 Washington. DC 20555 ULNRC. 0 3681 Gentlen en:
DOCKET NUMBER 50-483 CALLAWAY PLANT FEEDWATER ISOLATION CHANGES
References:
- 1) ULNRC-03628 dated August 8, IW7
- 2) ULNRC-03673 dated October 31,1997 In the Reference I license amendment application, Union Electric Company requested appmval for the installation of a bypass switch to block feedwater isolation on P-4 coincident with low T.,,. The significant hazards evaluation is hereby revised on page 5 of 8 in Attachment I to Reference 1 to remove the ambiguity as to when this isolation function would be restored. The wording is changed to clearly tie this restoration to an operational mode change, i.e., prior to entering MODE 2. This clarification does not alter the conclusions of either of the licensing evaluations attached to Reference 1.
In addition, as stated in Reference 2, the Nominal Trip Setpoints for the Vessel AT Power-1 and Power-2 portions of the SG Water Level Low-Low ESFAS trip function are being increased by 2.41 % RTP.
Please find attached a replacement page 5 mark-up for of Reference I and two replacement page mark-ups for Insert 3/4 3-25 of Attachment 3 of Reference 1.
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I If you have any questions on this amendment application, please contact us, t-Very tmly yours, g
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Alan C. Passwater Manager-Licensing and Fuels GGY/jdg 9711190317 971110 "
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PD8t ADOCK 05000483 P
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Alan C. Passwater, of lawful age, being first duly sworn upon oath says that he is Manager, Licensing and Fuels (Nuclear) for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By Alan C.
Passwater Manager, Licensing and Fuels Nuclear day SUBSCRIBED and sworn tc before me this of
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PATRICIAL REYNt1BS NOMAY PURUC-nUEOFungggg ST. Louts COWfW MYCokt8084011DFIMERm
1 cc:
M. H. Fletcher Professional Nuclear Consulting, Inc.
19041 Raines Drive Derwood, MD 20855-2432 Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive Suite 400 Arlington, TX 76011-8064 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Barry C. Westreich (2)
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 1 White Flint, North, Mail Stop 13E16 11555 Rockville Pike Rockville, MD 20852-2738 Manager, Electric Department Micsouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Ron Kucera Department of Natural Resources P.O. Box 176 Jefferson City, MO 65102 Don Woodlan TU Electric P.O. Box 1002 Glen Rose, TX 76043 Pat Nugent Pacific Gas & Electric Regulatory Services P.O. Box 56 Avila Beach, CA 93424
I Page 5 of 8 This bypass switch will be used during startup and shutdown evolutions 2.
with To,5564*F just prior to opening the reactor trip breakers. Plant conditions that would call for the restoration of the feedwater isolation function cannnot occur without opemtor action to close the reactor trip breakers. The administrative controls governing startups will also ensure that this bypass is manually defeated and the isolatior function restored de c~np!& 3:cd 'ro;,in:h;;, prior tgc!+; 'N "cr:r H;r
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In addition, t utomatic indication of the bypass is not required since the subject circuitry does not prodde a required safety function. Section 4.13 ofIEEE 2791971 and RG 1.47, Posinon C.3 allow the proposed use of an adminstratively controlled, manual bypass indication for an infrequently used bypass such as the one proposed.
50.92 EVALUATIONS The proposed changes to the Technical Specifications a involve a significant hazards consideration as discussed below.
Actuation Logic Applicability and New SG Water Level Imw-Iow Functional Unit 1.
Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
The proposed changes impose more stringent requirements and have been reviewed to ensure no previously evaluated accident has been adversely affected. The more stringent requirements are imposed to ensure the plant's operation and testing are consistent with the safety analysis and licensing basis.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
The proposed changes do not involve a physical alteration of the plant (ne new or differer.t type of equipment will be installed other than the bypass switch addressed in a separate 50.92 evaluation below) or changes in controlling parameters. The proposed changes do impose different requirements; however, these changes are consistent with assumptions made in the safety analysis and licensiv, basis. Actuation logic applicability is extended to MODE 3 and the SSPS slave relays that implement feedwater isolation on SG water level low-low will continue to be surveilled quarterly as they have always been tested. Thus,
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