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UNITED STATES i
NUCLEAR REGULATORY uGMMISSION y
C WASHINGTON, D. C. 20555 8
September 9,1980 a
f Docket No. 50-289 MEMORANDUM FOR:
Richard H. Vollmer, Director, Division of Engineering Brian K. Grimes, Program Director, Emergency Preparedness Program Office Denwood F. Ross, Director, Division of Systems Integration Robert M. Bernero, Director, Probabilistic Analysis Staff Frank Schroeder, Acting Director, Division of Safety Technology Caryle Michelson, Director, Office for Analysis and Evalua-tion of Operational Data FROM:
Thomas 11. Novak, Assistant Director for Operating Reactors, Division of Licens.ing
SUBJECT:
TMI-l HEARING - ADDITIONAL BOARD QUESTIONS At the prehearing conference conducted by the assigned Atomic Safety and Licensing Board on August 12-13, 1980, Board members posed additional ques-tions requiring testimony.
Advance copies of the questions were forwarded on August 22 & 26 to reviewers currently participating in testimony preparation in related areas or having expertise in the specific area of concern. provides a subject listing of the Board's concerns with the appropriate reference to the prehearing transcript.
DL requests a listing of the assigned reviewer (s) for each question by COB September 19, 1980 (cc to Harley Silver).
In some cases, support by other NRC organizations may be required to respond completely; each division is requested to solicit the support it requires.
If a question has been addresr.ed in previously submitted testimony please indicate by reference.
Efforts toward preparation of testimony in response to contentions should take precedence over efforts on these new requests. Responses to the Board's questions should be in the format of a restatement 'of the question followed-by a narrative response. ' Responses must be filed no later than October 8,1980.
c~Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing Enclosures & cc:
See next page 8009250 M
- g.,
RVollmer, BGrimes, Dross, RBernero,.
FSchroeder, CMichelson
Enclosures:
~
1.
Board Questions 2.
Prehearing Conference Transcript 2374-2399*
cc w/ enclosures 1 & 2:
DEisenhut cc w/ enclosure 1 only:ECase RKeinig VNoonan HDenton ZRosztoczy FHofmayer JZudans FPagano VanNiel RSatterfield RFitzpatrick PCheck TSpeis JMazetis WJensen RKreger WMurphy FCongel WPasciak JStolz
&!ermeil OELD-Tourtellotte, Christenberry, Cutchin JRosenthal RReid HSilver SWookey TNovak EHylton MErnst CBerlinger JKnight Glear WBivins TJohnson EAdensam RPurple J01shinski H0rnstein EBlackwood JHeltemes
- For Additional Copies of Transcript, Contact Sheryl Wookey X27435, Rm. 330A
THI-1 ItE ARING - BOARD QUESTIONS ADDf D AND ISSlffS RAISED DURING pREHEARING - AUGUST 12-13,-198D.
Subj ec_t Transcript Info previously Responsible Line t
Sm11 Break LOCA M 74 - 2380 kT. censen DS!
2'374 (2D)
Operation of RCp J. Zudans DSI 2376 (22)
Operat6r Action 2770(22)
Reliance Non-Safety Grade Equipment DSI 2376 (19) p0RV DE Fnvironiental Qualification - 2391 - 23M J. Zudans Reg. Guide 1.89 W. Jensen DE NUREG-0694-Applicab111ty 2390 - 2392 II. Sliver will Di/ Support by 2391 (16) 1.0.1 Control Room Design rpordinate Dif f S individually DL/ Support by 2391 (10)
II.E.1.1 AfW Reliability (Event Tree Logic)
DSI DL/ Support by 2391 (20)
II.B.8 Ruling on Degraded Core Accident DSI DI./ Support by 2391 (23)
II.B.7 liydrogen Control DSI Suf ficiency of Proposed 2392 H. Silver will DL/ Support by Short-Term & Long-Tenn coordinate All Divisions Ac tions Interim Reliability 2393 R. Bernaro DL/ Support by 2392 (16)
CR-3 IRtp Applicability to IMI-1 Cvaluation plan (IREp)
J. F1urphy Nuclear Regula-tnry Research (rAB)
G g
Offiite fionitoring 2393 N. VanNiel L pi'0 2393(6)
Offsite Ibnitoring Input To Response Center (Addressed to Licensee W. pasciak DSI 2393 (14) tbnitoring Background Radiation b
3
-Sta f f should be ready to discuss if necessary especially as relates to emergency response Q
center)
[M NUPEG-0660-As Applied To 2293 - 2394 H. Silver to DL Restart address Loss of Emergency Tecdwater 2394 - 2396 W. Jensen, J.
DSI 2394 (12)
Sa fety-Grade fquin. Requircinents (for main FW trans iont)
Wennell, J. Zudans USI 2391 (13)
Effect of loss of fa:I J. Sto17 R.
psg 2394 (16)
Operator Action Required-reed 1. D1ced l' ode w
fitzpatrick, C.
Osl
?394 (19-25)
Decay Heat Dissipation-Hpl pune Requirements b
Berlinger, C.
DSI 2395 (4-13)
Rellatrity of EfW; Vulnerability to Non-Safety Grade Michelson failures A operator errors, sources of power to turbine pumps IP.1 2395 (14-25)
Concerns Re: recil K, D1ced fbde A 2396 (1-5)
Safety $1qnificance oaf 0D/ DST 2396 (6)
Industry ixperience/ffW (Sa fety-Grade)
DL/ Support by 2396 (13)
NURfG-0667 - CR-3 Recommendations Deemed all divisions Applicable to Ifil J
as needed Ground Water Concerns 2397 - 2399 T. Johnson DE
.