ML20039B341
| ML20039B341 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 12/14/1981 |
| From: | Parker W DUKE POWER CO. |
| To: | Adensam E, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.2, TASK-2.K.2, TASK-2.K.2.13, TASK-2.K.2.17, TASK-2.K.2.19, TASK-2.K.3.01, TASK-3.A.1.2, TASK-TM NUDOCS 8112220554 | |
| Download: ML20039B341 (5) | |
Text
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DUKE PowEn COMPANY l'owen 13U11. DING 422 SouTu Cuuncu STREET, CHAH1DTTE. N. C. asc42 W8 LLI AM O. PA R M E R J R, December 14, 1981 r,,,,,,,0
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v c, e coe,c Sttaae Paooveno*e 373-4083 Mr. liarold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission g
Washington, D. C.
20555
,p 03 Attention:
Ms. E. G. Adensam, Chief g
N M.GO Licensing Branch No. 4 j
DEC 2119815 [
Re: McGuire Nuclear Station Docket No. 50-369 k, L
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Dear Mr. Denton:
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The McGuire Operating License, NPF-9, contains several licerts tions related to NUREG-0737 requirements which have various actions required by January 1, 1982.
The purpose of this letter is to give the status of each of these itens and provide justification for extension of the completion date fot' those items which r.ie not expected to be complete by January 1, 1982. A formal license amendment request is belng processed for submittal.
It is expected that this forthcoming 1 L nse amend-ment request will rely on the information presented in this letter for justification. summarizes the status of those conditions in the McGuire license which have or will have been satisfied by January 1,.1982. contains a dis-cussion on status of and justification for deferral of those items which will not be complete by January 1, 1982.
It should be noted that the items which will not be complete are not unique to McGuire Nuclear Station. Numerous other plants which have the same required completion dates in their license or through commitment to NUREG-0737 will not be able to meet the January 1,1982 date for many of the NUREG-0737 items.
Please advise if there are questions regarding this matter.
f Ver'y truly you s
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L William O. Parker, Jr GAC/jfw Attachments cc:
Mr. P. R. Bemis Mr. James P. O'Reilly, Director Senior Resident Inspector U. S.-Nuclear Regulatory Commission McGuire Nuclear Station Region II g
101 Marietta Street, Suite 3100
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Atlanta, Georgia 30303 5
8112220554 811210~
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PDR ADOCK 05000369 p
McGuire Nuclear Station License Conditions Which Will Be Satisfied by January 1, 1982 Post Accident Sampling (II.B.3) - 2.C.(11).C Sampling panels designed to enable high level samples of the Reactor Coolant System and Containment atmosphere are in the final phases of pre-installation checkout. These panels are scheduled to be installed by January 1, 1982.
Commission Orders on Babcock & Wilcox Plants. Subsequently Applied to all PWR Plants (II.K.2) - 2.C.(11)K
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(1) Analysis of Reactor Vessel During Recovery from Small Break LOCA with Loss of Feedwater (II.K.2.13)
The analysis required by this item is undergoing final review within the Westinghouse owner's Group and will b4 submitted by December 31, 1981. The report when submitted will satlify the requirements of this license condition.
'(2) Analysis of the Potential for Voiding in the Reactor Coolant System J
(II.K.2.17)
Westinghouse (in support of the Westinghouse Owners Group) has performed a study which addresses the potential for void formation in Westinghouse designed nuclear steam supply systems during natural circulation cooldown/
depressurization transients. This study'has been submitted to the NRC by the Westinghouse Owners Group (letter OG-57, dated April 20, 1981, R. W.
Jurgensen to P. S. Check) and is applicable to' McGuire Nuclear Station.
j In addition, the Westinghouse Owners Group has developed a natural circu-lation cooldown guideline that takes the results of the study into account so as to preclude void formation in the upper head region during natural circulation cooldown/depressurization transients, and specifies those conditions under which upper head voiding may. occur.. Thase Westinghouse Owners Group generic guidelines have been submitted to the NRC (letter 0G-64, dated November 30, 1981, R. W. Jurgensen to D. G. Eisehhut). The generic guidance developed by the Westinghouse Daners Group (augmented as j
appropriate with plant specific considerations) will be utilized in the j
implementation of McGuire plant specific operating procedures. This l
condition is considered to be satisfied.
L (3) Benchmark Analysis of Sequential Auxiliary Feedwater Flow to the Steam Generators Following a Loss of Main Feedwater (II.K.2.19) i Subsequent to the inclusion of this condition in the McGuire Operating l
License, the NRC staff completed a generic review of this subject.
It was concluded that no further action was necessary for Westinghouse plants with U-tube steam generators. Attachment 1A is a June 29, 1981 letter from r-er,-w--
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Mr. Steven A. Varga, NRC/0NRR, to Duquesne Light Company which documents this conclusion.
Since this concern is not applicable to McGuire, no response is required thus this condition is satisfied.
Upgrade Emergency Support Facilities (III.A.I.2) - 2.C.(II)n A functional description of the upgraded meteorological systen for McGuire is being prepared. When submitted this report will s.itisfy the license requirement associated with this item.
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UNITED STATES C
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June 29,1981 fiOV 301981
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Docket No. 50-334 Mr.'J. J. Carey, Vice President Duquesne Light Company Nuclear Division Post Office Box 4 Shippingport, Pennsylvania 15077
Dear Mr. Carey:
SUBJECT:
ELIMINATION OF ITEM II.K.2.19 (SEQUErlTIAL AUXILIARY FEEDWATER FLOW ANALYSIS) REQUIREMENT FOR LICENSEES WITH NSSSs DESIGNED BY W AND CE We have completed a generic review on this subject and conclude that no further action is necessary since the concerns expressed in Item II.K.2.19 of the TMI Action Plan, as clarified in NUREG-0737, are not considered applicable to NSSSs with inverted U-tube steam generators such as those designed by Westinghouse and Conbustion Engineering.
We consider this item to be complete and therefore you' are not required to respond to Item II.K.2.19 of the TMI Action Plan.
Sin.cerely,{}
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e Operating R: actors Br'anch #1 l
Divisioti of Licensing cc:
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McGuire Nuclear Station License Conditions Which Will Require Extension Beyond January 1, 1982 Inadequate Core Cooling Instruments (II.F.2) - 2.C.(11)f (1) Reactor Vessel Level Instrumentation System This item is addressed in a November 11, 1981 letter to the NRC. A specific request for extension of this condition along with the requisite justification was included in this letter. Although a schedule extension has been requested, work has continued toward completion of the system.
During the current unscheduled outage which commenced in early December, vacuum fill and hydraulic balancing of the system was started. However, a problem with some of the system piping was discovered.during this process.
This will result.in some additional delay. Consequently, the requested extension is still needed.
(3) Upgraded. Thermocouple System This item requires the incore thermocouple system to meet a revised set of design criteria in the areas of performance, qualification and operator interface. At the time this condition was included in the McGuire license, Duke Power Company concluded that satisfying these requirements by January 1, 1982 was a virtual impossibility because of the nature of the changes that would be required and the relatively short time available to accomplish them.
In a letter to the NRC on April 23, 1981 Duke provided its assessment of the installed thermocouple system and stated its intent to persue develop-ment of a thermocouple system which would meet the criteria in NUREG-0737.
Toward this end Duke has done the following:
(1) Requested a proposal from Westinghouse for an upgraded system (2) Evaluated the separation of thermocouple cables for compliance with 10 CFR 50 Appendix R (See my October 21, 1981 letter to Mr.
Harold R. Denton)
(3) Evaluated the survivability of the cables associated with the incore (core exit) thermocouples (See " Analysis of Hydrogen Control Measures at McGuire Nuclear Station", Section 5.0, submitted to the NRC staff on October 31, 1981.)
(4) Increased the range of the backup display to 23000F from the original 700 F.
In spite of the above efforts, a final system design has not been developed.
Technical problems have delayed the proposal from Westinghouse such that a firm date for receipt of a proposal has not been established. Once a proposed system design is received it must be evaluated against other related requirements.
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a These include control room design review requirements, safety parameter display system requirements, Regulating Guide 1.97 requirements and NUREG 0588 requirements to name a few.
It is Duke Power Company's conclusion that extention of the implementation date beyond January 1, 1982 does not involve any adverse safety considerations.
The evaluation of the currently installed system against the NUREG-0737 criteria is contained in my April 23, 1981 letter to Mr. Harold R. Denton. Also the Standby Shutdown Facility has the capability to monitor three incore thermo-couples independent of the control room readouts thus giving the system addi-tional reliability.
A specific license amendment request which will outline the proposed implemen-tation schedule will be submitted in a few days.
This schedule will provide for upgrading the in-containment portion of the system by the first refueling of Unit 1.
The outside containment parts of the system would be modified to meet final criteria on the same schedule that changes emanating from the control room design review are implemented. This would assure that the impact of any changes to the thermocouple system are properly integrated with other related requirements.
Final Recommendation of B & O Task Force (II.K.3) - 2.C.(11)1 (2) Revised Small Break LOCA Model.
This item requires that the analysis methods used by NSSS vendors and/or fuel suppliers for small-break LOCA analysis for compliance with Appendix K to 10 CFR Part 50 be revised, documented, and submitted for NRC approval.
Westinghouse feels very strongly and Duke Power Company agrees that the small-break LOCA analysis model currently approvdd by the NRC for use on McGuire Nuclear Station is conservative and in conformance with Appendix K to 10 CFR Part 50.
However, (as documented in letter NS-TMA-2318, dated September 26, 1980, T. M. Anderson to D. G. Eisenhut) Westinghouse believes that improvement in the realism'of small-break calculations is a worthwhile effort and has committed to revise its small-break LOCA analysis model to address NRC concerns (e.g. NUREG-0611, NUREG-0623, etc.) This revised Westinghouse model is currently scheduled for submittal to the NRC by April 1, 1982 as documented in letter NS-EPR-2524, dated November 25, 1981, E. P.
Rahe to D. G. Eisenhut.
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