ML17297A839
| ML17297A839 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/16/1981 |
| From: | Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Tedesco R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0623, RTR-NUREG-623, TASK-2.K.3.05, TASK-TM ANPP-18938-JMA, NUDOCS 8109210116 | |
| Download: ML17297A839 (9) | |
Text
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ACCESSION iNBR t 810 FACIL'rtSTN 50" 528 STN SO 529 STN 50 530 AUTH',NAME VAN BRUNT'lq Krs REC IP ~ NAME{
TEDESCOi R,. Lr, 9210116'OC
~ DATE.: 81/09/16 NOTARI ZKDt YES Palo Verde Nucleari Stationr Unit-ir Arizona Publi Palo Verde Nuclear Station~. Unit 2i Arizona Publi Palo. Verde Nuclear Station~
Unit 3i, Arizona Publi AUTHOR AFFILIATION Arizona Public Service Co.
REC'IPIENT AFFIL>>IATION Assjstant Directori for Licensing OOCKK>>Ti g 05 5WEP'5000529>>,
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SUBJECT:
For wards supplemental response to QA Branch Question<
260
~ 62'.(c) aper NRC 810904 I tl L TMI Item II~ K ~ 3 ~ 5>> re automatic tr ip, of reactor coolant pumps"'uring LOCA..
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'HOENIXiARIZONA 65036 September 16, 1981 ANPP-18938-JMA/WFQ Mr. R. L. Tedesco Assistant Director of Licensing Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3
Docket Nos.
STN-50-528/529/530 File:
81-056-026'.1.10
Reference:
Letter from E. E. Van Brunt, Jr. to R. L. Tedesco,
" dated September 4,
1981
Dear Mr. Tedesco:
Attached please find our supplemental response to the NRC Quality Assurance Branch Question 260.62(c).
This response supplements our response to NRC Question 260.62(c) transmitted in the referenced letter.
Please contact me if you have any questions.
EEVBJr/WFQ:skc Attachment cc:
J. Spraul (NQC) (w/a)
J. Kerrigan (w/a)
P. Hourihan (w/a)
A. C. Gehr (w/a)
Very truly you s, cu t E. E. Van Brunt, Jr.
APS Vice President Nuclear Projects ANPP Project Director i'109210iib 8109~lb, PDR ADOCK 05000528 i A PDR
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STATE OF ARIZONA
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E. E. Van Brunt Jr.
, represent that I am Vice President NuclearPro'ects of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.
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Su lemental Res onse 260.62 c
C.l As the design of this item progresses, it will be identified in Table 3.2-1 appropriately.
C.6 Refer to response for Item a.7 and Table 3-2.1; Item 20, Sheet 26 of 36.
C.7 The auxiliary feedwater system initiation is part of the Engineered Safety Features Actuation System identified on Table 3.2-1, Item 7, Sheet 6 of 36.
Auxiliary feedwater flow indication is a safety-related system and is covered by Item 7 of Table 3.2-1, Sheet 6 of 36 (.'M.loother systems required for safety.")
C.14 Currently, PVNGS Units 1, 2 and 3 do not have an automatic trip of the reactor coolant pumps in the case of a small-break LOCA. Refer to CESSAR Appendix B, Item II.k.3.5.
(Copy Attached)
C.16 Administrative control of the emergency plan and the emergency kits, protective equipment and supplies maintained for emergency purpose~
is considered to be a quality-related activity and as such is subject to the pertinent requirements of the operations quality assurance program.
C.18 Refer to response for Items a.9 a.l7.
C.19 Identified on Table 3.2-1 (Item 15, Sheet 21 of 36)
II.K.3.5 AUTOMATIC TRIP OF REACTOR COOLANT PUMPS DURING LOSS-OF-COOLANT ACCIDENT
SUMMARY
Tripping of the reactor coolant pumps in case of a loss-of-coolant accident (LOCA) is not an ideal solution.
Licensees should consider other solutions to the small-break LOCA problem (for example, an increase in safety injection flow rate).
In the meantime, until a better solution is found, the reactor coolant pumps should be tripped, automatically in case of a small-break LOCA.
The signals designated to initiate the pump trig"are discussed in NUREG-0623.
RESPONSE
As an activity for the C-E Owners
- Group, Combustion Engineering is preparing predictions of the LOFT Test L3-6.
Documentation of the C-E Owners Group's plans for such test prediction and response to related NRC requirements is provided in the Letter of July 31, 1980, "Test Analysis of Loft Small Break Test L3-6," G. Liebler; C-E Owners Group, to P.
S.
- Check, USNRC.
Because of the importance of those tests, C-E concurs with the NRC position provided in the clarification to this Action Item and will defer a final decision on implementation of automatic trip of reactor coolant pumps until the evaluation of ECC models is completed.
Amendment No.
2 March 12, 1981
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