ML20041B075
| ML20041B075 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/16/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.3, TASK-2.K.2.13, TASK-2.K.3.05, TASK-TM NUDOCS 8202230241 | |
| Download: ML20041B075 (3) | |
Text
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TENNESSEE VALLEY AUTHORITY N6*We"s?effitr'e"eWo5eFil' E
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February 16, 1982 g,
2 FEB 22WM n%%YO Director of Nuclear Reactor Regulation 9
Attention: Ms. E. Adensam, Chief TDC s
Licensing Branch No. 4 g
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Division of Licensing g
,j U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Ms. Adensas:
In the Matter of
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Docket Nos. 50-327 Tennessee Valley Authority
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50-328 In response to D. G. Eisenhut's October 31, 1980 letter which transmitted NUREG-0737, " clarification of TMI Action Plan Requirements," TVA has previously provided responses in accordance with the schedule specified by the NRC. Enclosed is a supplemental response for items II.K.2.13, II.K.3 5, and II.D.3 for Sequoyah Nuclear Plant.
If you have any questions concerning this matter, please get in touch with J. E. Wills at FTS 858-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY d'
S L. M. Mills, nager Nuclear Regulation and Safety Sworn to and subscribed before me this // Y ay of b h. 1982 d
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My C salon Expires 4/
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Enclosure cc:
U.S. Nuclear Regulatory Commission Region II Attn: Mr. James P. O'Reilly, Regional Administrator 3Oo/
101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 S
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8202230241 820216 PDR ADOCK 05000327 An Equal Opportunity Employer N
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ENCLOSURE SUPPLEMENTAL RESPONSE FOR NUREG 0737 TMI ACTION PLAN REQUIREMENTS SEQUOYAH NUCLEAR PLANT NUREG-0737 Item II.K.2.13 This item requires a detailed analysis of the thermal-mechanical con-ditions in the reactor vessel during recovery from small breaka with an extended loss of all feedwater. Westinghouse Electric Corporation (in support of the Westinghouse Owners' Group) has performed an analysis for generic Westinghouse plant groupings to address this issue which was submitted to NRC on December 30, 1981 as WCAP-10019, " Summary Report on Reactor Vessel Integrity for Westinghouse Operating Plants."
This generic stuoy is applicable to Sequoyah and will be referenced if additional efforts are necessary to completely address NRC concerns (e.g., plant specific analyses).
NUREG-0737 Item II.K.3.5 Westinghouse (in support of the Westinghouse Owners' Group) has performed an analysis of delayed reactor coolant pump trip during small-break LOCAs. This analysis is documented in reference 1.
In addition, Westinghouse (again in support of the Westinghouse Owners' Group) has performed test predictions of LOFT experiments L3-1 and L3-6.
The results of these predictions are documented in references 2, 3, and 4.
Baset! ':7 (1) the Westinghouse analysis, (2) the excellent prediction of the.J/I experiment L3-6 resc1ts using the w.estinghouse analytical model, and (3) Westinghouse simulator data related to operator response time, the Westinghouse and TVA position is that automatic reactor coolant pump trip is not necessary since sufficient time is available for manual tripping of the pumps.
Our understanding of the schedule for final resolution of this issue is:
A.
Once NRC formally approves the Westinghouse model, a 3-month study period will ensue during which the Westinghouse Owners' Group will demonstrate compliance with some NRC acceptance criteria for manual RCP trip. The NRC acceptance criteria will accompany their-formal approval of the Westinghouse models.
B.
If, at the end of the 3-month period, the Westinghouse Owners' Group has been unable to show compliance with the acceptance criteria, NRC will formally notify utilities that they must submit an automatic RCP trip design.
o euy REFERENCES 1.
" Analysis of Delayed Reactor Coolant Pump Trip During Small Loss of Coolant Accidents for Westinghouse Nuclear Steam Supply Systems,"
WCAP-9584 (proprietary) and WCAP-9585 (non-proprietary), August 1979 2.
Letter 08-49 dated March 3, 1981, R. W. Jurgensen (Chairman, Westinghouse Owners' Group) to D. F. Ross, Jr., (NRC).
3 Letter 08-50 dated March 23, 1981, R. W. Jurgensen (Chairman, Westinghouse Owners' Group) to D. F. R.3s, Jr., (NRC).
4.
Letter 08-60 dated June 15, 1981, R. W. Jurgensen (Chairman, Westinghouse Owners' Group) to P. S. Check (NRC).
NUREG-0737 Item II.D.3 Our previous response to NUREG-0578 (page 13) which addressed this item stated the following:
"The flow indicator module gives positive indication of the fully open and fully closed position of each valve." This is changed to read:
"The flow indicator module will be calibrated to detect indication of failure of a valve to reclose." This alerts the operator of a valve failing to reclose when the resulting flow is substantially smaller than would otherwise cause an alarm.
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