ML19318A420
| ML19318A420 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point, Susquehanna, Columbia, Limerick, LaSalle, Zimmer, Shoreham, Bailly File:Long Island Lighting Company icon.png |
| Issue date: | 05/30/1980 |
| From: | Teh-Chiun Su Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19318A421 | List: |
| References | |
| REF-GTECI-A-39, REF-GTECI-CO, TASK-A-39, TASK-OR NUDOCS 8006230001 | |
| Download: ML19318A420 (4) | |
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gQQf agqMBB Distribution Central Files GIB R/F NRR R/F R. Mattson F. Schroeder K. Kniel P. Norian P. Check J. Miller R. Tedesco T. Novak J. Kudrick D. Ross D. Eisenhut J. Knight W. Butler R. Bosnak F.'Schauer T. Su C. Anderson L. Shao, RES G. Lainas C. Grimes L. Rubenstein i
S. Fabic, RES T. Lee', RE5' R. K. Frahm Sydney Min r Richard Stark Chen P. Tan Anthony Bournia J. Wilson J. Kudrick y
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UNITED STATES s
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Generic Task A-39
. Docket Nos: '50-358, 50-352/353, 50-367, 50-373/374, 50-387/388, 50-410, 50-322, 50-397 APPLICANT:. Members of Mark II Owners Group
SUBJECT:
MEETING WITH MARK II OWNERS GROUP TO DISCUSS SUPPRESSION P0OL TEMPERATURE RESPONSE TO SRV ACTUATIONS, APRIL 10, 1980 Back'round g
The purpose of this meeting was to discuss the technical details related to suppression pool temperature response to safety / relief valve actuations.
In addition, the Stanford Research Institute (. SRI) on behalf of one applicant (Susquehanna Steam Electric Stations, Units 1 and 2) was to
- present the experimental and analytical results related to the concern l
for suppression pool temperature limit.
An attendance list and a copy of the meeting handouts are enclosed.
Summary The Mark II Containment Lead Plant Program Load Evaluation and Accep-tance Criteria, NUREG-0487, specifies the suppression pool local tem-perature _ limit of 200 F.
It also requests that all. applicants analyze the su)pression pool temperature response to SRV actuations to demonstrate that tie individual plant will be operated under this limit.
Mr. Metcalf of Stone & Webster presented the SRV events, key assumptions for each event,' and the preliminary results for the lead plants. The events evaluated for the Mark II owners group included a stuck-open SRV during power, an isolation scram, and a small LOCA.
In performing the analysis for suppression pool response to these events, the Mark II owners group assumed that the operator would scram the reactor immediately when the suppression pool reaches the Technical
~ Specification limits. Another significant assumption us_ed'in the analysis for stuck-open SRV during full power operation was that the ' main condenser would be available as a heat sink to absorb energy and mass released
'from_the reactor through the bypass system. These two key assumptions were the main-items of discussion. No detailed justification for these assumptions was provided in the' meeting.
ys
. Mr. R. -Frahm of RSB questioned the justification related to the assemp-tion of using the main condenser as a heat sink since the bypass system is a non-safety' grade system. He also expressed concern regarding the events selected to calculate the suppression pool temperature limit.
Additional information will be required to demonstrate that the " worst" case-for suppression ~ pool temperature response to SRV operation has been analyzed.
With respect to the assumption that the RHR system would be available for pool cooling mode following a small break LOCA, we advised the Mark II Owners group to investigate the validity of this assumption. We
. indicated that the LPCI mode of the RHR system takes first preference when a LOCA signal is initiated. Also, some RHR pumps may be diverted for wetwell cooling for certain plant unique designs.
Dr. M. Sanai of SRI International presented the results of the study on steam condensation performance for the T-quencher device. The object of this study was_to assess performance of the PP&L T-quencher when saturated temperatures are approached in the suppression pool. This study included evaluation of all quencher related data.
Results of the study indicated that Lthe T-quencher device performed satisfactorily for pool temperatures near or at saturated conditions. The potential for the violent collapse of large steam bubbles is minimum because of the relatively good mixing expected in.the suppression pool. Therefore, the study concluded that a limit on pool temperature is not needed.
We indicated that. SRI's study provided new information regarding the concern on suppression pool temperature limit. We also requested the applicants to. submit detailed information, which contains proprietary information~, for further evaluation.
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T. M. Su, Task Manager Generic Task A-39 Generic Issues Branch Division of Safety Technology
Enclosure:
As stated cc: See next page i
cc:
L. D. Steinert, GE Jason Post, GE F. C. Rally, GE R. F. McClelland, GE R.' J. Muzzy, GE LV. Gupta, GE C. E. Conomos, BNL
. Richard Stark, PP&L D.-F. Roth, PP&L P.
E'. Taylor R. W.-Riley, CG&E-J. S. Abel, CE H. W. Vollmer,- Phil ~ Electric Co.
H. Chan,.Long Island Lighting Company-d 4
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Mark II Owners Group /NRC Meeting April 10,.1980 T. M. Su NRC/ DSS /CSB J.~E..Metcalf S&W C. E._Conomos BNL/NRC R. K. Frahm NRC/ DSS /RSB T. M. Lee NRC/00R/PSB L. D.-Steinert GE Sydney Miner NRC/DPM Richard Stark NRC/DPM Larry Schell PP&L Chen P. Tan' NRC/ DSS /SEB
-Anthony Bournia-NRC/DPM~
Jason Post GE-G. R. Abrahamson-SRI J. A. lleyandt -
Bechtei D. F. Roth PP&L R. W. Riley CG&E K. J. Green Sargent & Lundy J. S.' Abel Commonwealth Edison
'D.-M. O' Conner.
Bechtel Power Corp.
H. W. Vollmer-Philadelphia Electric Company F. C._ Rally GE
.R.'F. McClelland GE R.-J. Muzzy GE A..J. Wheeler Science Applications (For GE)
G. J._Uram NUTECH (MK I)
P. E. Taylor PP&L E. R. Klein NMPC F. E. Ogden NMPC H. R. Johnson Ebasco J. Wilson NRC/DPM J. Kudrick NRC H.~ Chan Long Island Lighting Company G. E. _Gottfried Sargent & Lundy R. Grunseich Burns & Roe
-V. Gupta S&W W. M. Davis GE l
M.-R.'Granback NIPSCO M. Sanai SRI International S.~Zorrilla-ININ/CFE-
-A.' Giowz ININ/CFE l
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