ML19318C280
| ML19318C280 | |
| Person / Time | |
|---|---|
| Site: | Fermi, Susquehanna, Columbia, LaSalle, Zimmer, Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 06/19/1980 |
| From: | Joshua Wilson Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8007010297 | |
| Download: ML19318C280 (46) | |
Text
.
t' O
JUN 191980
. MEETING
SUMMARY
DISTRIBUTION Docket' File' G. Lear NRC PDR V. Noonan Local PDR S. Pawlicki
- TK1 V. Benaroya NRR Reading Z. Rosztoczy LB#1 Reading W. Haass H. Denton D. Mullar E. Case R. Ballard D. Eisenhut W. Regan R. Purple D. Ross B. J. Youngblood
- o. Check A. Schwencer k Satterfield Branch Chief, LB#3
- 0. Parr J. Miller F. Rosa
-G. Lainas W. Butler R. Vollmer W. Kreger J. P. Knight R. Houston R. Bosnak T. Murphy F. Schauer L. Rubenstein R. E. Jackson T. Sreis Project Manager J. N. Wilson' Branch Chief, Core Performance Attorney, OELD J. Stolz M. Rushbrook S. Hanauer OIE (3)
N. Gammill ACRS (16)
R. Mattson R. Tedesco
'F. Schroeder D. Skovholt NRC
Participants:
M.
nst C. Berlinger K. Kniel G. Knighton Branch Chief. Rel, & Risk Assessment Br.
BCC: Apolicant & Service List 8007010 %
9' 9
[4 i
llNITED STATES NUCLEAR REGULATORY COMMISSION 3
,g WASHINGTON, D. C. 20665 e
.... +,/
.)UN 191980 Docket Nos.
50-358 50-397 50-322 50-341 50-373 50-387 APPLICANTS: Cincinnati Gas & Electric Company Long Island Lighting Company Commonwealth Edison Company Detroit Edison Company Pennsylvania Power & Light Company Washington Public Power Supply System FACILITIES:
Zimer 1, Shoreham 1, LaSalle 1, Fermi 2, Susquehanna 1, WNP-2
SUBJECT:
SUfHARY OF MEETING HELD ON JUNE 13, 1980 A meeting was held in Bethesda, Maryland with the above named members of the Boiling Water Reactor - Licensing Review Group (BUR-LRG).
The purpose of the meeting was to brief the staff on the development of concensus positions on RSB and ICSB open issues from the LaSalle docket. The list of attendees for this meeting is provided in Enclosure 1.
The meeting began with a review of the organization and function of the BWR-LRG. Copies of the agenda and viewgraphs are enclosed. The BWR-LRG had met for several days prior to the meeting to develop concensus positions on open issues from the LaSalle docket. The results of this effort were provided as LRG draft working papers on ICSB and RSB open issues (see enclosures).
Two of the issues, RSB-ll and RSB-20, were used as examples to describe the working papers. These working papers will be reviewed in detail at subsequent meetings with representatives of the respective review branches at a future date.
Similar working papers will be developed for open issues from other review branches and for TMI issues.
N. W son, NRC Manager r BWR-LRG
Enclosures:
As stated cc: w/ enclosures See next page l
Mr..D. Louis Peoples Director of Nuclear. Licensing Connonwealth Edison Company P.' O. Box 767 Chicago, Illinois 60690 cc:
Richard E. Powell, Esq, Isham, Lincoln & Beale
.0ne First National Plaza 2400 Chicago, Illinois 60670 Dean Hansell, Esq.
Assistant Attorney General State of Illinois 188 West Randolph Street Suite 2315 Chicago, Illinois 60601 Mr. Roger Walker, Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 737 Streator, Illinois 61364
. 1 r
Long Island Lighting Company ccs:
Howard L. Blau, Esq.
Blau and Cohn, P.C.~
217 Neubridge Road Hicksville, New York 11801 Jeffrey Cohen, Esq.
Deputy Commissioner and Counsel New York State Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223 Energy Research Group, Inc.
400-1 Totten Pond Road Waltham, Massachusetts 02154 Irving Like Esq.
Reilly, Like and Schnieder 200 West Main Street Babylon, New York 11702 J. P. Novarro Project Manager Shoreham Nucit.' Power Station P.O. Box 6]8 Wading River, New York 11792 W. Taylor Reveley, III, Esq.
Hunton & W11114ms P. O. Box 1535 -
Richmond, Virginia 23212 Ralph Shapiro, Esq.
Canner & Shapiro 9 East 40th Street New York, New York 10016 Edward J. Walsh, Esq.
General Attorney Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Resident inspector /Shorenam NPS c/o U.S. Nuclear Regulatory Commission P, 0. Box B Rocky Point, New York 11778
-- - - - ~ -, -
I
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LongIslandLightingCompany ccs (continue,d)
Honorable Peter Cohalan Suffolk County Executive
-County Executive /Legislati Building Veteran's Memorial Highway Hauppauge, New York l'788 David Gilmartin, Esq..
Suffolk County Attorney County Executive /Lcgislative Building Veteran's Memorial Highway Hauppauge, New York 11788 MHB Technical Associates 1723 Hamilton Avenue - Suite K San Jose, California 95125 Stephen Latham, Esq.
Twomey, Latham & Schmitt P. O. Box-398 33 West Second Street Riverhead, New York 11901 Joel Blau, Esq, New York Public Service Commission The Governor Nelson A. Rockefeller Bldg.
Emoire State Plaza Albany, New York 12223 i
Mr.' Norman W. Curtis Vice President - Engineering and Construction Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 cc: Mr. Earle ti. Mead Project Engineering Manager Mr. Robert J. Shovlin Project Manager Pennsylvania Power & l.ight Company Pennsylvania Power and Light Co.
2 3rth Ninth Street 2 North Ninth Street niientown, Pennsylvania 18101 Allentown, Pennsylvania 18101 Jay Silberg, Esq.
Shaw, Pittman, Potts &
Matias F. Travieso-Diaz, Esq.
Trowbridge Shaw, Pittman, Potts &
1800 M St reet, N. W.
Trowbridge 1800 M Street, N. W.
Washington, D. C.
20036 Washington, D. C.
20036 Mr. William E. Barberich, Nuclear Licensing Group Supervisor Dr. Judith H. Johnsrud Co-Director Pennsylvania Power & Light Company Environmental Coalition on 2 North Ninth Street Nuclear Power Allentown, Pennsylvania 18101 433 Orlando Avenue Edward M. Nagel, Esquire State College, PA 16801 General Counsel and Secretary Pennsylvania Power & Light Company Mr. Thomas M. Gerusky, Director Bureau of Radiation Protection 2 North ninth Street Department of Environmental Allentown, Pennry1vania 18101 Resources Bryan Snapp, Esq.
Commonwealth of Pennsylvania P. O. Box 2063 Pennsylvania Power d Light Company Harrisburg, PA 17120 901 Hamilton Street Allentown, Pennsylvania 18101 Ms. Colleen Marsh Robert M. Gallo Box 538A, RD#4 Resident Inspector Mountain Top, PA 18707 P. O. Box 52 Mrs. Irene Lemanowicz, Chairperson Shickshinny, Pennsylvania 18655 The Citizens Against Nuclear Dangers Susquehanna Environmental Advocates P. O. Box 377 c/o Gerald Schultz, Esq.
RD#1 500 South River Street Berwick, PA 18503 Wilkes-Barre, PA 18702
-John L. Anderson Oak Ridge National Laboratory Union Carbide Corporation Bldg. 3500, P. O. Box X Oak Ridge, Tennessee 37830
E 6
LWashingt'on Public Power Supply System a
ces:
~ Joseph B. Knotts, Jr., Esq.
Debevoise & Liberman-1200 Seventeenth Street, N.
W.-
Washington, D. C. 20036 Richard Q. Quigley, Esq.
- Washington.Public Power Supply System P. O. Box 968 Richland, Washington 99352 Nicholas Lewis, Chairman Energy Facility Site Evaluation Council 820 East Fifth Avenue Olympia, Washingcon 98504 Mr. O. K. Earle Licensing Engineer P. O. Box 968 Richland, Washington 99352 Resi. dent Inspector /WPPSS-2 NPS c/o U.S. Nuclear Regulatory Commission P. 0. Box 69 Richland, Washington 99352 4
8
.i
.)
Dr. Wayne H. Jens Assistant Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 cc:
Eugine B. Thomas; Jr., Esq.
Mr. Jeffrey A. Alson LeBoeuf, Lamb, Leiby & MacRae 772 Green Street, Building 4 1333 New Hampshire Avenue, N. W.
Ypsilanti, Michigan 48197 Washington, D. C.
20036
' David E. Howell, Esq.
Peter A. Marquardt, Esq.
21916 John R Co-Counsel Hazel Park, Michigan 48030 The Detroit Edison Company 2000 Second Avenue Mrs. Martha Drake Detroit, Michigan 48226 230 Fairview Petoskey, Michigan 49770 Mr. William J. Fahrner Project Manager - Fermi 2 William J. Scanlon Esq.
The Detroit Edison Company 2034 Pauline Boulevard 2000 Second Avenue Ann Arbor, Michigan 48103 Detroit, Michigan 48226 i-Mr. Larry E. Schuerman Licensing Engineer - Fermi 2 Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 Charles Bechhoefer, Esq., Chairwan Atomic Safety & Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. David R. Schink Department of Oceanography Texas A & M University College Station, Texas 77840 Mr. Frederick J. Shon Atomic Safety & Licensing Board Panel U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Mr. Earl A. Borgmann Vice President - Engineering Cincinnati Gas & Electric Company P. O. Box 960 Cincinnati, Ohio 45201 cc:
Troy B. Conner, Jr., Esq.
David B. Fankhauser, PhD Conner, Moore & Corber 3569 Nine Mile Road 1747 Pennsylvania Avenue, N. W.
Cincinnati, Ohio 45230 Washington, D. C.
20006 Dr. Frank F. Hooper Mr. William J. Moran School of Natural Resources General Counsel Ann Arbor, Michigan 48109 Cincinnati Gas & Electric Company P. O. Box 960 lis. Augusta Prince, Chairperson Cincinnati, Ohio 45201 601 Stanley Avenue Cincinnati, Ohio 45226 Mr. William G. Porter, Jr.
Porter, Stanley, Arthur Charles Bechhoefer, Esq., Chairman and Platt Atomic Safety & Licensing Board 37 West Broad Street Panel Columbus, Ohio 43215 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. Steven G. Smith, Manager Engineering & Project Control Mr. Glenn 0. Bright Dayton Power & Light Company Atomic Safety & Licensing Board P. O. Box 1247 Panel Dayton, Ohio 45401 U. S. Nuclear Regulatory Commission J. Robert Newlin, Counsel
~
~
Dayton Power & Light Company Leah S. Kosik. Esq.
P. O. Box 1247 3454 Cornell Place Dayton, Ohio 45401 Cincinnati, Ohio 45220 Mr. James D. Flynn, Manager W. Peter Heile, Esq.
Licensing Environmental Affairs Assistant City Solicitor Cincinnati Gas & Electric Company Room 214, City Hall P. O. Box 960 Cincinnati, Ohio 45220 Cincinnati, Ohio 45201 Atomic Safety & Licensing Boa,rd Mr. J. P. Fenstermaker Panel Senior Vice President-0peratione U. S. Nuclear Regulatory Commission Columbus & Southern Ohio Washington, D. C.
20555 Electric Company 215 North Front Street Atomic Safety & Licensing Appeal Columbus, Ohio 43215 Board U. S. Nuclear Regulatory Commission David liartin, Esq.
Washington, D.
C'.
20555 Of fice of the Attorney General 209 St. Clair Street First Floor i
Frankfort, Kentucky 40601 l
l
- Mr. Ear' A. Borgmann.
cc:
Resident Inspector /Zimmer U. S. Nuclear Regulatory Commission P. O. Box 58 New Richmond, Ohio 45157 4.
Dale D. Brodkey Assistant Attorney General Division of _ Environmental Law Office of the Attorney General 209 St. Clair Street Frankfort, Kentucky 40601 0
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ENCLOSURE Name Organization 0.* Keener Earle WPPSS Fra,nkSvetkovjch ZPS John Gouvas LaSalle Roger Boyd KMC, Inc. (LRG Group)
Lou De1 George Comm. Ed. - LaSalle Jerry N. Wilson NRC Themis Speis NRC Faust Rosa NRC/ Power Sys. Br.
M. D. Lynch NRC W. E. Barberich PP&L R. M. Stark NRC J. P. Morin LILC0 Dick Johnson GE Larry E. Schuerman DE John R. Ellwanger Burns & Roe E. Connell, III Bechtel Ed Urata GE P. S. Check NRC Wayne Hodges NRC I. A. Peltier NRC R. M. Satterfield NRC Olan Parr NRC A. Bournia NRC M. Srinivasan NRC J. Knox NRC R. J. Pruski S&L M. E. Jackson S&L J. D. Flynn Cincinnati Gas & Electric G. F. Dawe Stone & Webster J. T. Murphy Stone & Webster
AGENDA LRG/NRC MEETING BETHESDA, MD JUNE 13, 1980 1.
DISCUSSION OF LRG PROGRESS A.
COMMUNICATIONS B.
MECHANICS 2.
REVIEW RSB/IECSB WORKING PAPERS A.
PROPOSED CLOSURE BASES B.
APPROVED CLOSURE BASES (ZPS SER)
C.
OL IMPACT 3.
REQUIRED NRC RESPONSE A.
NEED ISSUE REVIEWERS l
B.
NEED LEAD PLANT REVIEWERS C.
DOCUMENT CLOSURE O
LRG DOCKET 4.
TMI ISSUES A.
SAME LRG PROCESS B.
.REauEST LEAD PLANT REVIEW 5.
FUTURE MEETING SCHEDULE l
A.
RSB/I&CSB E/0 JUNE B.
TMI EARLY JULY
+
C.
EQB JULY D.
PSB JULY E._
C.SB JULY w q -
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6/13/80 MECHANICS I,
REVIEW ISSUES - NTOL ACTION, NRC SUPPORT
~
A.
IDENTIFY ISSUES UNRESOLVED COMMON B.
IDENTIEY CLOSURE STATUS EACH DOCKET ~
FORMAL.
INFORMAL C.
APPLY CLOSURE STATUS EACH DOCKET WHEREVER POSSIBLE D.
RESOLVE REMAINDER CONSENSUS POSITION WHEREVER POSSIBLE ADDRESS OTHERS AS PLANT UNIQUE II.
RESOLUTION OF ISSUES - NRC ACTIONI NT0L SUPPORT REVIEW CLOSURE BASES
-CONSENSUS POSITIONS B.
-APPLICATION FORMAL CLOSURE BASES ALL DOCKETS C.
DOCUMENTATION ISSUE LEAD PLANT SER DDRMEN OTHER NTOL DOCKETS l
i I
F
- N **
l 4@Jaa- - -
=f(
.i__..-
_, _. mm RESOURCES NT0L BWR lMARKI/II NSAC 5EIER[
WORKING TMI 0WNERS II/PO ELECTRIC GROUP OWNERS GROUP EPRI GENERIC GROUP
-AIF.
- ETC,
-. +,... - -
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. 1 COMMUNICATION
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EXISTING '
NRC 4-
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ORGANIZATIONS j
a g _ _._.._1._ -- 2 a
UTILITY NT0L NRC ORGANIZATION NTOL -
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.f ORGANIZATION
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_, COMMON
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LRG DRAFT WORKING PAPER-6/13/80 ISSUE ICSB-2 Physical Separation and Electrical Isolation (7.1.4, 7.2.3 and 7.5.3)
In the applicant's design, class IE instrumentation do not adhere to adequate separation criteria, have not been qualified, and do not adhere to separation of Class 1E to non-class 1E instrumentation POSITION (Unique) l Itjis judged that this review should be made on a plant specific basis.
Regulatory Guide 1.75 is not applicable to any of the plants in the LRG.
Th9 degree of conformance to this Regulatory Guide has been addressed ~on each docket and has in the case of the Zimmer. docket been accepted (SER 8.1.2 and'8.3.3)
REFERENCE LSCS ZPS SHOREHAM FERMI WPPS SUSQUEllANNA open closed open open open Q31.280(N) SER 8.3.3 Q223.12(N)
I Q31.92(N)
Q32.49(N)
\\
8.1.2 Q223.67(N)
LRG DRAFT WORKING PAPER 6/13/80 ISSUE ICSB-3 ATWS POSITION (Common)
See Issue RSB-22
a v
LRG DRAFT WORKING PAPER 6/13/80 ISSUE I
ICSB-4j Test Techniques (7.1.4)
In order to perform routine surveillance testing, it is necessary for the applicant to pull fuses.
We consider that this design does not satisfy the requirements of IEEE Std 279-1971 Paragraphs 4.11 and 4.20.
POSITION (Unique)
This issue is considered to be plant specific and will not be addressed by LRG.
4 REFERENCE 1
i LSCS ZPS SHOREHAM FERMI WPPSS
_SUSQUEHANNA_
O open closed open open Q31.284 Q31.061(N)
Q32.33(N) l
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I l
L 1
LRG DRAFT ~ WORKING PAPER 6/13/80 ISSUE ICSB-5 Safety System Setpoints (7.1.4)
The range of class 1E system sensors may be exceeded in the worst-case combination of setpoint and accuracy.
_ POSITION (Unique)
This issue is considered to be plant specific and will not be addressed by LRG..
Technical justificatiori for the setpoints and allowable values are expected to be made available during tech. spec. review.
REFERENCE i
LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEllANNA open open open open Review Review-Review Q31.234(N)
W/TS W/TS W/TS
LRG DRAFT WORKING PAPER 6/13/80 ISSUE-ICSB-6 Drawings - (7.14, 7.3.3.and 7.6.3 The one line drawings and schematics contradict the functional control drawings and system description which are provided in the FSAR.
Furthermore, contact utilization charts contradict the actual schematics.
POSITION (Unique)
This issue is plant unique.
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LRG DRAFT WORKING PAPER 6/13/80.
- ISSUE--
-ICSB RCIC Classification-RCIC should be.~ classified. safety grade.
POSITION (Common)
See issue RSB-6 t
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-7 LRG DRAFT WORKING PAPER
, 6/13'/ 80 l-
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ISSUE
-(7.6.3)
ICSB-10 Rod Block Monitor The applicant does not agree that the rod block monitor is a protection system.
F POSITION (Common)
The NRC has conducted an extensive review of the Rf1CS including refueling interlocks,RBM, RWM, RSCS on various dockets.
Plants with open items havina similar designs will be con-
~
formed to the Zimmer design (i.e., the resolution will be reviewed and resolution bases if applicable will be incor-porated).
The Zimm'gr design review has'been completed and the issue resolved \\(Ref. 2).
This closure basis will be relied upon.
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4 REFERENCE ~
1 '.
Multiple Chapter 7. questions.on~ all dockets 2.
-Responses to Zimmer Questions 221.374and221b376.
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LRG. DRAFT WORKING PAPER 6/13/80 ISSUE ICSB-11 MSIV Leakage Control System (7.6.3)
We identified a single fai. lure to the MSIV leakage control system which could lead -to' possible failure of ohe system during testing or operation.
POSITION (Common) i The design of the MSIV - LCS will be modified to eliminate the single failure concern.
This modification will be equivalent as that accepted on the Hatch and Zimmer dockets.
REFERENCE i
LSCC ZPS SHOREHAM FERMI WPPS SUSQUEHANNA open closed N/A open open i
\\
Q31.076(N)
Q31. 283 (N )
Q221.362(N)
8 LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-1 In ternally Generated Missiles - (3.5.1)
The applicant has not supplied the information to show that all saf ety-rela ted systems and components within containment, including the containment, are protected from missiles.
With regard to missiles sizes of concern, what is the valve size
~
below which, if failure should occur in a high pressure system, damage to other components within the primary containment would not be significant? State the criteria used to determine this size.
Identify all valves in the primary containment larger than this size and identify the missile protection provided for each valve (either physical location or barrier).
POSITION (Unique)
Each applicant, on a plant specific basis, will demonstrate acceptability using one of, or a combination of, the following:
1.
Provjde p'rotection from internally generated missiles.
2.
Perform Analysis to show tnat missiles are not generated, or, if generated, have insufficient energy to cause unacceptable damage.
This item relates to ACRC generic concernII-8, recirculation pump overspeed during a LOCA.
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REFERENCE i
g
@N LSCS ZPS SP3REHAR FERMI WPPS SUSQUEHANNA
\\
open
' closed open open open open EN Q212.3(N)
SER 3.5.1 Q212.21(N) Q212.132(U) Q212.016(N)
@d kN 3.
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LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-2 Control Rod System - (4.6.2)
As a result of eliminating the control rod drive system return line, we are reviewing generically.with regard to the-impact on control rod drive system performance.
Consequently, we require the applicant submit sy' stem performance data directly applicable to La Salle and will require the applicant to conform to the conclusion of the generic study as. applicable to La Salle.
POSITION (Common) 1.
Remove the CRD return line and cap the vessel -nozzle.
Acceptability is demonstrated by GE analysis of CRD performance characteristics.
2.
The CRD line is left routed to the vessel.
The line is administratively closed by valving it out during operation. CRD performance must be demonstrated.
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3.
The CRD return line is rerouted to another vessel entry point (e.g. feedwater line).
CRD performance is unchanged, assuming acceptable return path established.
IGSCC is corrected by the reroute.
NOTE: 1.
The LRG members acknowledge the receipt of the NRC letter " modifications to Boiling Water Reactor Control Rod Drive Systems" in March,1980 and will factor the concerns of the letter into their documented positions.
- 2. GE Letter reports dated March 14, 1979 (G.G. Sherwood to V. Stello/R. Mattson) and May 2,1980 (R. Gridley to
- 0. Eisonhut) address all NRC concerns for vessel makeup capability.
REFERENCE
(
LSCS ZPS
'5HOREHAM FERMI WPPS SUSQUEHANNA open closed open open open open (pos. 1 )~
(pos. 2)
(pos. 1)
(pos. 3)
(pos. 1)
(pos. 1)
- (212.147(N)
(
212.69(N) 211.19(N) 211.43(N) t l
LRG DRAFT WORKING PAPER; 6/13/80 ISSUE RSB-3 Safety / Relief' Valves (5.2.2_and 6.3.2)
Additional information is required both for qualification tests and operating experience with the applicant's safety / relief valves.
POSITION (Common) 1.
Provide evaluation and operatingLhistory.
See Owners Group response to position 2.1.2 of NUREG-0578.
2.
Participate in TMI.' Qualification Program (II.D.1) s T
REFF.RENCE LSCS ZPS SHOREHAM FERMI WPPS SUSQUEHANNA open open.
open open open open Q212.131 ( N )
SER 5.2.2 Q212.62(N)
Q212.133(U) Q211.51(U) Q211.70(N)
Q212.69(N)
Q212.79(N)
e LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-4 Trip of Recirculation Pumps to Mitigate ATWS (5.2.2)
We require reperformance of the over pressure protection analysis to consider the effect of the ATWS RPT.
POSITION
- The over pressure protection report will be resubmitted to demonstrate compliance with the ASME Pressure Vessel Code, considering the addition of ATWS RPT.
This position was acceptable on the Zimmer docket as noted by official NRC meeting minutes for a March 28, 1979 meeting.
This item is resolved-for Zimmer.
REFERENCE
_L_S C S ZPS S110REHAM FERMI WPPS SUSQUEllANNA open closed open open opeil open Q212.136(N)
Q212 75 Q212. 52 (N )
212.45A(N) Q211.101 211.71(N)
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-5
' Detection of Intersystem Leakage (5.2.5)
We requested that the applicant show how it intends to detect leakage from the reactor coolant systems into both the low pressure.
coolant injection (3 trains) and low pressure core spray systems as required by Regulatory Guide 1.45.
POSITION (Unique)
The LRG members will demonstrate conformance to Regulatory Guide 1.45(4) with reliance on level instru-mentation, pressure instruments, and/or radiation monitors REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open closed open open open Q212.138( N )
SER 5.2.5 Q212.25(N) 211.09(N)
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LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-6 Reactor Core Isolation Cooling Pump Suction (5.4.1)
The applicant must supply further information to determf 2 whether.
the RCIC pump suction has to be automatically switched from the condensate storage tank to the suppression pool in the event of a safe shutdown earthquake and concomitant failure of the condensate storage tank.
POSITION (Common)
The qualification of RCIC will be resolved by insuring the availability of a Seismic Category I water source.
This will be achieved by:
1.
Provide a seismic category 1 CST, or 2.
Provide an automatic switchover to the suppression pool, or 3.
Provide justification for a manual switchover to the suppression pool.
NOTE:
a)
This position satisfies the requirement identified in NUREG-0660 item II.K.3(C.3.22).
b)
It is not an OL item in accordance with NUREG 0694.
Compliance with C.3.22, verify procedures, will be accomplished prior to fuel load on Jan. 1, 1981, whichever is later.
Compliance with design modification will be accomplished by Jan. 1, 1982.
c)
Also resolves issue ICSB-7.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open closed closed open open open (pos. 2)
(pos. 2)
(pos. 1)
(pos. 3)
(pos. 2) 212.14)(N)
SER 5.4.3 &
212.57(N) 211.46(N) 7.3.3
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-7 Shutdown Unintentionally of the Reactor Core Isolation Cooling System (5.4.1)
"Show how the design of the RCIC protection syster. prevents unintentional shutdown of the system, when the system is required, because of spurious ambient temperature signals from areas in and around the_ system (especially in the RCIC pump room)."
(COMhcAJ)
POSITION 1.
The temperature alarm setpoint will be established by calculating a heat balance for the normal room environment, and then introducing the heat release cause by an alarm limit leak.
Actual ambient tempera-ture settings will be -determined during startup testing.
NOTES:
1.
CEC 0's notes of LaSalle/NRC Meeting of October 11, 1979 item 3.i indicate that LaSalle response to Q212.130 was sa ti s f a c to ry.
2.
NUREG-0660 Task II.K.3 item C.3.15 is related to the I
issue discussed above.
Although this NUREG-0660 is not a requirement for licensing of the LRG plants (Ref. NUREG-0694), the BWR (TMI) Owners Group is addressing that task and the utilities represented by the LRG are participating in that effort.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open i
open open open 212.130(N) 212.30(N) 211.10(N) 211.33(N)
I
LRG DRAFT-WORKING PAPER 6/13/80 ISSUE RSB-8
-Residual Heat Removal System (5.4.2)
The applicant must perform tests to show that flow through the sifety/ relief valves is adequate to provide the necessary fluid relief required consistent with the analyses reported in Section 15.2.9 of-the FSAR.
POSITION (Common) 1:
Crosby Valves, e.g. LA SALLE
- Demonstrate by analysis (based on valve characteristics such as internal dimensions) that the valve (s) will pass sufficient water to allow a forced cooldown to be maintained.
2:
Target Rock (2 stage), e. g. SHOREHAM - Demonstrate by shop test of a valve that (1) the valve can be opened by low pressure water and (2) once open is maintained open and passes sufficient flow to maintain a forced cooldown.
3:
Provide a backup to RHR shutdown cooling which does 4
not utilize the SRV in the alternate ~cooldown mode.
NOTE:
NUREG-0660 Task II.D.1 is related to the issue discussed above.
This task is identified as a requirement for licensing of LRG plants (Ref: NUREG-0699).
The BWR (TMI) Owners Group is addressing that task and the-utilities represented by the LRG are participating in this effort.
REFERENCE LSCS 2PS SHOREHAM FERMI WPPS SUSQUEHANNA
( C ro s b'y )
(Crosby)
(Target ' Rock) (Target Rock) (Crosby)
(Crosby) open open open open open 212.137(N) 212.62(N) 212.65(U) 211.25(N) 211.8(N) 212.69(N) 212.79(N) l
~~'
LRG DRAFT WORKING PAPER 6/13/80
' ISSUE RSB-9 Categorization of Valve which Isolate RHR from Reactor Coolant System
- (5.4.2)
We require that the valves which serve to isolate the residual heat removal system from the reactor coolant system be classified category A/C in accordance with the provisions of Section XI of the ASME core.
RSB-13 Leakage 8 Testing of Valves Used to Isolate
( 6. 3. 2.)
We require periodic testing and establishment of leak rate criteria for the valves that isolate the reactor coolant system from all the emergency core cooling system.
POSITION (Common)
Containment isolation valves which also provide isolation between high and low pressure systems will be tested in accordance with ASME Section XI as well as Appendix J to 10CFR50.
Exemption from ASME Section XI requirements will be requested if it can be demonstrated the requirement is met on an alternate basis.
NOTE:
Exemptions will be requested REFERENCE LSCS ZPS SHOREHAM FERMI WPPS SUSQUEHANNA open closed open open open open Q212.137(N)
SER 5.4.2 Q212.106(N)
Q212.25(N) Q211.74(U)
Q211.97(U)
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-10 Available Net Positive Suction Head - (6.3.2)
The applicant must verify that the suction lines in the suppression pool leading to the ECCS pumps are designed to preclude adverse vortex formation and air injection which could effect the pumps p e r fo rma n c e.
POSITION (Unique)
The issue is regarded as plant unique and requires plant specific review of system design details.
REFERENCE MCS ZPS SHOREHAM FERMI WPPSS SUSQUEHAN_NA, open closed closed open open open Q212.127(N)
SER 6.3.2 Q041.22(N) Q212.77(U) 211.61(U) 211.62(U)
LRG DRAFT WORKING PAPER 6/13/80 I_SSUE RSB-ll Assurance of Filled ECCS Line (6.3.2)
Ins trumentation is not 'sufficiently sensitive to detect voids at -
the top of-ECCS pipe' lines.
The applicant must provide adequate instrumentation to assure filled ECCS lines.
p0SITION (Unique) 1.
Jockey pump system on same division as system being filled.
2.
Pressure and/or flow switch on pump discharge with control room annunciation.
3.
Tech. Spec. surveillance.
NOTE:
This position is applicable to LSCS, ZPS, SNPS, and WPPSS.
Because of de~sig6 differences plant unique review is required on Fermi-2 and SSES dockets.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open closed closed open open open-0212.134(N) SER 6.3.2 Q212.59 Q212.125(U) Q212.79(U)
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-12 Operability of ADS (6.3.2, 5.4.2 The applicant must show that the air supply for the ADS is sufficient for the extended operating time required and assures us by reliability data that the ADS valves will function as required.
POSITION (Common)
The applicant will review and document that the ADS system design satisfies the expressed concern.
NOTES:
a)
The ADS system for Zimmer which is a typical design has been accepted by the NRC.
b)
CECO's La Salle/NRC meeting notes of October 11, 1979 item 3L indicate issue as closed.
La Salle's
' ADS system is identical to Zimmer's.
c)
NUREG-0660 Task II.K.3 item C.3.28 is related to the issue discussed above.
This task is not identified as a requirement for licensing of LRG plants (Ref: NUREG-0694).
The BWR(TMI) owners group is addressing that task and the utilities represented by the LRG are participating in that effort.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SilE0llFHANNA open closed open open open open i
Q212.132-1(N) SER 6.3.2 Q212. 97(N) Q212. 24 A('N)' Q211.48(N )
Q211.67(N) 9.3.1
,y-
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-14 Operability of ECCS pumps (6.3.2)
The applicant must provide assurance that the ECCS pumps can function for an extended time (maintenance free) under the most limiting post-LOCA conditions.
POSITION (Common)
This issue has been closed on Zimmer and Shoreham dockets on the basis of information presented in response to NRC questions.
Similar information has been provided on the rest of the dockets.
NUREG-0660 Task II.B.2 is related to the issue discussed above and is being addressed by the BWR TMI Owners Group.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPS
_SUSQUEHANNA 4
open closed closed open open open Q212.128 (N )
Q212.67A(U)
Q211.72(N)
Q211.106(N)
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-15 Additional LOCA Break Spectrum (6.3.4.)
The applicant was requested to submit two additional LOCA analyses to complete the La Salle break spectrum.
These were as follows:
a)
The design basis accident with a discharge
~
coefficient of 0.6, and b)
A small break analysis for a recirculation beak of 0.02 square feet.
POSITION (Common)
Lead plant bounding approach valid and confirmed by all additional analyses performed (Ref LaSalle Q212.125).
No additional plant specific analysis will be provided other than that already provided by each plant for the limiting failure / break combination.
REFERENCE LSC6 ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open Lead Plant Sister Plant
- Sister Plant
- open Sister Plant
- BWR-5 BWR-4 BWR-4 BWR-5 BWR-4 Q212.129(N)
Q212.66(N)
Q211.68(U) 211.107(N)
- Lead BWR-4 plant is Brunswick
LRG DRAFT WORKING PAPER 6/13/80-ISSUE RSB-16 LOCA Analysis _-
(6.3.4)
The applicant analyzed a coincident instantaneous closurg of a flow control' valve during a LOCA which resulted in a 300 F increase in peak clad temperature.
We requested that this accident be reevaluated considering more realistic valve closure dynamics.
POSITION (Common - BWR/5 Only)
No additional analysis is required because the failure described represents a non-mechanistic failure mode.
In reality, for all failure modes except valve hydraulic system failure, the valve fails as is, which is physically limited to at least 20% open.
If the hydraulic system fails, the valve will drift closed, but at a design rate of no more than 10t 1% per second.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open N/.A N/.A open N/A Q212.143( N )
Q211.83(N)
LRG DRAFT WORKING PAPER
-6/13/80 ISSUE RSB-18 Diversion uof Low' Pressure Coolant Inf ection System.-(6.3.4)
Low pressure coolant injection flow can be diverted to wetwell ~ and drywell spray and. suppression pool cooling.
The applicant must demonstrate that adequate core cooling is maintained when diversion is considered.
p0SITION (Common)
The limiting break will be reviewed with LPCI diversion af ter. 600 sec to confirm that the peak clad temperature -
-limit is not exceeded and adequate core cooling is maintained.Such analyses have been performed for Zimmer and LaSalle (BWR-5) and Shoreham (BWR-4).
These analyses confirm the acceptability 0.f LPCI diversion at'600 sec.
The ~ applicability of these results to the other LRG plants will be verified.
T
)
REFERENCE p
LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open open open open open Q212.126 (N )
Q221.377 SNRC 296 212.8 Q211.82(U)
Q211.105
-LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-19 Failure of the Feedwater Controller (15.1 )
The applicant's analysis for the failure of-the feedwater controller indicates that the temperature drop is no greater than 100F.
At a domestic boiling water reactor an actual feedwater temperature occurred which demonstrated a temperature difference of 150 F.
The applicant must justify the decrease in temperature drop used for this event or recalculate the transient by using a justified tempera-ture decrease to assure conformance with applicable criteria.
POSITION (Common)
Analyses have been performed on the lead plant. assuming a AT = 1500F-(which bounds observed operating experience) for the LFWH event.
LaSalle (BWR-5) has completed this calcula-tion (see Amendment 49) confirming the conclusion that the results are insensitive tos$T assumed and is not a limiting event.
The applicability of these results to the other LRG plants will be verified.
REFERENCE 1
_U TJ3 ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open open open open Q212.142(N)
Q212.41A(U) 211.87(U) 211.XXX(U) t I
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RS8-20 Use of Nonreliable Equipment in Anticipated Operational Transients
( 15.1 )
la analyzing anticipated operational transients, the applicant took credit for equipment which has not been shown to be reliable.
Our position is that this equipment be identified in the technical specifications with regard to availability, setpoints and surveil-lance testing.
The applicant must submit its plan for implementing this requirement along with any. system modification that may be required to fulfill the requirement.
POSITION (Common)
This issue is related to a long time concern by the NRC Re:the use of non-safety grade equipment to mitigate transients.
Many questions were asked on many dockets relative to:
a)
Credit for Non class 1E relief function vs. IE safety functions setpoints.
b)
Credit for RPS inputs from the turbine b1dg.
c)
Credit for Level 8 turbine trip and turbine bypass system.
As a result of this concern GE and the NRG met (Nov. 78) for a comprehensive review of all such transients and as a result of that meeting, determined the most limiting " event" which takes credit for non-safety grade equipment was the excess feedwater transient relying on the L-8 turbine trip and turbine bypass.
NRC concurred-that providing technical specifications for the L-8 trip and the turbine bypass Nalves satisfactorily resolves this issue.
All LRG plants commit to this except Fermi-2.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPS SUSQUEHANNA open closed open open open open Q212.144(N) Q212.74(N) Q212.104(N) Q212.64A(U) -Q211.XXX(U) Q211.114. (N)
ACRS Transcript
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-21 Use of Non-Safety Grade Equipment in Shaf t Seizure Accident (15.2)
The applicant included the use of non-safety grade equipment in his analyses for shaf t seizure and shaf t. break accidents.
We require tha t these accidents be reanalyzed without allowance for the use of non-safety grade equipment.
POSITION (Common) 1.
The evaluation basis for the subject event was reviewed and accepted on the Zimmer docket (SER 15.2).
2.
A qualitative assessment of the event without reliance on non safety grade equipment suggests that the applicant's conclusion (i.e. the event is bounded by the nRA LOCA event) would not change.
3.
The non-safety grade equipment in question have been reviewed in item RSB-21 and steps have been taken to improve their reliability.
4.
No further analysis is required.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open closed open open i
Q212.135 ( N,'. SER 15.2 Q211.92(U)
Q211.120(N)
LRG DRAFT WORKING PAPER 6/13/80 ISSUE
.RSB-22 ATWS (15.2.1)
We require that the applicant agrees to implement plant modifications on a scheduled basis in conformance with the Commission's final resolution'of ATWS.
In the event that La Salle starts operation before necessary plant modifications are implemented, we require some interim actions be taken by La Salle in order to reduce, further, the risk-from ATWS events.
The applicant will be required to:
1)
Develop emergency procedures to train operators to recognize an ATWS event, rod position indicators, flux monitors, vesselincluding consideration of s level and pressure indicators, relief valve and isolation valve indica tors, and containment temperature,- pressure, and radiation indicators.
2)
Train operators to take actions in the event of an ATWS including consideration of immediately manual scramming the reactor by using the manual scram buttons followed by changing rod scram. switches to the scram position, stripping the feeder breakers on the reactor protection system power distribution buses, opening the scram discharge volume drain valve, prompt actuation of the standby liquid control system, and prompt placement of the RHR in the pool cooling mode to reduce the severity of the containment conditions.
POSITION (Common)
ATWS RPT plus procedure will be proavided by Fuel Load.
NOTE:
All LRG applicants are willing to implement alternate 2 on a best effort schedule as the basis for final resolution of the ATWS issue.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA Q212.105(N) 1
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-23 Peach Bottom Turbine Trip Tests (4.4.1) (4.4.2)
These-tests-must be evaluated and assess using the ODYN computer.
code.
We have not completed our review of the ODYN Code.
l POSITION (Common)
The LRG members agree to perform ODYN calculation (s) for the limiting pressure transients utilizing option B (GE/NRC generic resolution in process - estimated resolution sunmer -
1980)of the NRC letter dated 1/23/80.
LaSalle (lead plant) schedule for completion of calculation is Octo'ver 1980.
NOTE:
REDY is still an acceptable code for other transients.
REFERENCE LSCS ZPS SHOREHAM FERMI WPPSS SUSQUEllANNA open open open open open Q221.13(N)
Q212.75(N)
Q212.147(U) Q211.49(U)
Q211.68
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-24 MCPR (4.4.1)
(4.4.2)
(15.1)
After comp 1.etion of overpressure analysis, the minimum critical
. power ratio must be recalculated taking into consideration the turbine trip without bypass event.
The transient of generator load rejection without bypass results in an MCPR equal to 1.02 which is below the Safety limit of 1.06.
_The applicant classified this event an infrequent occurrence which would allow some-fuel damage.
We do not concur with this classification for this event. and we require that the operating limit be modified to satisfy the MCPR limit of 1.06.
POSITION (Common)
The LRG members agree to perform 0DYN calculations for the limiting pressure transients utilizing option B (GE/NRC generic resolution in process - estimated resolution summer 1980))of the NRC letter dated 1/23/80.
LaSalle (lead plant schedule for completion of calculation is Oct 1980.
Note that we understand REDY is still an acceptable code for other transients.
REFERENCE LSCS' ZPS SHOREHAM FERMI WPPSS SUSQUEHANNA open open open open open open
. Q212.129(N) Q212.75(N)
Q212.104(N) Q212. ll4(U)
Q211.84(U)
Q211.ll2(N) i
LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-25 GEXL Correlation (4.4.1)
Although we conclude that the GEXL correlation is acceptable for initial core load, we are concerned that GEXL correlation may not be conservative for reload operation.
The applicant, in a letter dated March 7, 1979, committed to incorporate the latest approved form of GEXL correlation at the time of reload for La Salle.
License Condition.
POSITION (Common) 1.
For first core cycle, GEXL is conservative.
Adequate negative worth is provided by the co' trol n
system to assure shutdown capability.
2.
The applicant (s) commit to incorporate the latest approved form of GEXL correlation at the time of reload.
4 REFERENCE I
LSCS ZPS SH0REHAM FERMI WPPSS SUS _QUEHANNA open closed open open open open Q221.10(N)
SER4.3.4 Q221.27(N)
Q230.3(N)
Q221.13(N)
Q221.3(N)
O LRG DRAFT WORKING PAPER 6/13/80 ISSUE RSB-26 Stability Evaluation (4.4.1)
In order to provide additional margin to s'tability limits, natural circulation operation of La Salle will be prohibited until our generic review of hydrodynamic stability characteristics is completed.
In addition, the La Salle stability analysis was performed for first cycle.
We will require that a new analysis be submitted and approved' prior to second cycles operation.
The applicant, in a letter dated March 7,1979, committed to perform, as part of the future reload analyses to update the hydrodynamic stabili ty analyses.
License condition.
POSITION (Common)
Sufficient documentation of stability margin for Cycle 1 has been presented for issuance of an opdrating license.
The 8
stability margin analysis will be updated as required for future reload applications.
This issue is addressed under generic NRC task action plan ([ TAP)
B-19.
REFERENCE i
LSCS ZpS SHOREHAM FERMI WPPSS SUSQUEHANNA Condition closed closed open open open for OL for OL
\\
SER 4.4.1 Q221.14 Q230.8(N)
Q221.09(N)
Q221.ll(N)
-_