ML20041B612
| ML20041B612 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 02/12/1982 |
| From: | Hernan R Office of Nuclear Reactor Regulation |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| ISSUANCES-OL, ISSUANCES-OM, NUDOCS 8202240354 | |
| Download: ML20041B612 (9) | |
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Docket Nos: 50-329/330 011. OL RECEIVED g.
FEB17;gggs : 1 fiEMORAliDUM FOR:
Llinor G. Adensaa. Chief anej"Qg
/
Licensing Bronch No. 4. OL roc 4?
FROH:
Ronald Hernan. Project llanager 6
~
Licensing branch No. 4. DL
SUBJECT:
h0TICE OF MEETING - IIIULAhD. UNITS 1 AND 2 DATE & TIllE:
February 23, 1982 8:30 AM - 4:00 Pti LOCATION:
Room P-ll4 Phillips Building Bethesda. Horyland PURPOSL:
To resolve reraaining Instrumentation and Control SER Open Iteus (Chapter 7).
1/
PARTICIPrwTS:
NRC Consumers Power Company H. Lee B. Horshe et al.
T. Dunning R. Hernan Argonne National Lab bechtel S. Halverson D. Lewis. et al.
Babcock and Wilcox
- b. Gray 6
Ronald W. Hernan. Project llanager Licensing Branch No. 4 Division of Licensing
Enclosure:
Agenda r
cc:
See next page 1/ ileetinos between hkC technical staff and applicants for licenses are open W interested menbers of tt e public, petitioners, intervenors, or v ier l
emcry -g.gg4 " parties"to attend es-observe rs. pursuant.to. ".Open..heeti ng..and.Statene it..o.f.......
> R,i,legnan,: e,b.fiRC..;it4 f,f.f.ol.) gy",,,33 Federa 1.hegister 28uS8. 6../.28./.78
""".-k 7 /. a-/R2 8202240354 820212 PDR ADOCK 05000329 E
PDR OFFICIAL RECORD COPY e uscro mo_m m
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'k UNITED STATES NUCLEAR REGULATORY COMMISSION h.
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WASHINGTON, D. C. 20555 FEB 1. da2 Docket Nos: 50-329/330 OM, OL NEMORANDUM FOR:
Elinor G. Adensam, Chief Licensing Branch No. 4, DL FROM:
Ronald Hernan, Project Manager Licensing Branch No. 4. DL
SUBJECT:
NOTICE OF MEETING - MIDLAND, UNITS 1 AND 2 DATE & TIME:
February 23, 1982 8:30 AM - 4:00 PM LOCATION:
Room P-ll4 Phillips Building Bethesda, Maryland PURPOSE:
To resolve remaining Instrumentation and Control SER Open Items (Chapter 7).
1/
PARTICIPANTS:-
NRC Consumers Power Company H. Lee B. Horshe, et al.
T. Dunning R. Hernan Argonne National Lab Bechtel S. Halverson D. Lewis, et al.
Babcock and Wilcox B. Gray 87,/tdr
/
Ro
. Hernan, roject Manager Licensing Branch No. 4 Division of Licensing Encicsure:
Agenda cc:
See next page 1/ Meetings between NRC technical staff and applicants for licenses are open for interested members of the public, petitioners, intervenors, or other parties to attend as observers pursuant to "Open Meeting and Statement of NRC Staff Policy", 43 Federal Register 28058, 6/28/78.
r MIDLAND Mr. J. W. Cook Vice President Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201 cc:
Michael I. Miller, Esq.
Mr. Don van Farrowe, Chief Ronald G. Zamarin, Esq.
Division of Radiological Health Alan S. Farnell, Esq.
Departnent of Public Health Isham, Lincoln & Beale P.O. Box 33035 Suite 4200 Lansing, Michigan 48909 1 First National Plaza
- Chicago, Illinois 60603 William J. Scanlon, Esq.
2034 Pauline Boulevard James E. Brunner, Esq.
Ann Arbor, Michigan 48103 Consumers Power Corpany 212 West Michigan Avenue U.S. Nuclear Regulatory Commission Jackson, Michigan 49201 Resident Inspectors Office Route 7 Ms. Mary Sinclair Midland, Michigan 48640 5711 Summerset Drive Midland, Michigan 48640 Ms. Barbara Stamiris 5795 N. River Stewart H. Freeman Freeland, Michigan 48623 Assistant Attorney General State of Michigan Environmental Mr. Paul A. Perry, Secretary Protection Division Consumers Power Company 720 Law Building 212 W. Michigan Avenue Lansing, Michigan 48913 Jackson, Michigan 49201 Mr. Wendell Marshall Mr. Walt Apley Route 10 c/o Mr. Max Clausen Midland, Michigan 48640 Battelle Pacific North West Labs (PNWL)
Battelle Blvd.
Mr. Roger W. Huston SIGMA IV Building Suite 220 Richland, Washington 99352 7910 Woodmont Avenue Bethesda, Maryland 20814 Mr. I. Charak, Manager NRC Assistance Project Mr. R. B. Borsum Argonne National Laboratory Nuclear Power Generation Division 9700 South Cass Avenue Babcock & Wilcox Argonne, Illinois 60439 7910 Woodmont Avenue, Suite 220 Bethesda, Maryland 20814 James G. Keppler, Regional Administrator U.S. Nuclear Regulatory Connission, Cherry & Flynn Region III Suite 3700 799 Roosevelt Road Three First National Plaza Glen Ellyn, Illinois 60137 Chicago, Ellinois 60602
Mr. J. W. Cook cc: Commander, Naval Surface Weapons Center ATTN:
P. C. Huang White Oak Silver Spring, Maryland 20910 Mr. L. J. Auge, Manager Facility Design Engineering Energy Technology Engineering Center P.O. Box 1449 Canoga Park, California 91304 Mr. Neil Gehring U.S. Corps of Engineers NCEED - T 7th Floor 477 Michigan Avenue Detroit, Michigan 48226 Charles Bechhoefer, Esq.
Atomic Safety & Licensing Board U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Mr. Ralph S. Decker Atomic Safety & Licensing Board l
U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. Frederick P. Cowan l
Apt. B-125 6125 N. Verde Trail Boca Raton, Florida 33433 Jerry Harbour, Esq.
Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission I
Washington, D. C.
20555 l
Geotechnical Engineers, Inc.
ATTN: Dr. Steve J. Poulos 1017 Main Street l
Winchester, Massachusetts 01890 l
MEETING NOTICE DISTRIBUTION Docket File NRC PDR NRC PARTICIPANTS Local PDR TIC H. Lee NSIC T. Dunning TERA R. Hernan LB #4 r/f E. Case D. Eisenhut/R. Purple T. Novak S. Varga D. Vassello R. A. Clark R. Tedesco E. Adensam J. Youngblood bec: Applicant & Service List A. Schwencer f
F. Miraglia J. R. Miller G. Lainas D. Crutchfield W. Russell R. Vollmer W. Johnston D. Muller R. Mattson L. Rubenstein T. Speis B. Grimes J. Kramer S. Hanauer F. Schroeder M. Ernst ACRS (16)
Attorney, 0 ELD Ol&E (3)
OSD (7)
Receptionist J. LeDoux, I&E I&E Headquarters
.I&E Region I I&E Region II I&E Region III I&E Region IV I&E Region V Project Manger R. Hernan Licensing Assistant u
n.;
D. Hood h
AGENDA lie:3
~
~. : Cc71GG 1.
.htify the RCS flow measur:.
its share ccrcn instu.nt line (FSAR Fig. 7.2-s).
2.
Provide status on setpoint methodology for the reactor trip instrument channels and the engineered safety features actuation instrument channels.
N
~
3.
Discuss safety grade anticipatory reactor trip system sensors qualifica-tion, cable routing criteria, and Technical Specification surveillance requirements.
4.
Discuss decay heat removal system letdown isolation valves diverse interlock (non-conformance to BTP ICSB-3).
5.
justify the bypassing automatic actuation signals to the chilled
/..
water safeguard pumps by' a transfer switch.
6.
Identify and justify all safety interlocks which cannot be tested during normal operation.
A
(
7.
Provide a failure modes and effects analysis for the PORV block valve i
I interlock bypass during a shutdown bypass mode of operation.
8.
Provide-status on evaluation of control grade system failures caused by malfunctions of common power source or instrument line.
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I
9.
Discdss cMr.nel scparation crit. aria for F?S shu'.da.r. bypass switch.
10.
Discuss single failure criteria for RCS letdown isolation valve arrangements.
11.
Discuss Technical Specification surveillance requirement on safe shutdown system.
12.
NI/RPS grounding concerns.
eD T
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=
1 4
(
Action Da t e Due 1)
Provide response to IE Sulletin 79-22 2/15/82
(
Reference:
ICSB Question 4) 2)
Revise FSAR Ta'ble 7.3-6 to clarify 2/15/82 that those cooponents. listed as excep-tions to Regulatory Guide 1.22 will be tested during shutdown conditions, and provide justification for not testing during power operation (
Reference:
ICSB Question 7)
To be determined 3)
Evaluate providing reset capability 6n seal in AFWAS to the AFW 1evel control valve in addition to capability pre-sently provided by FOGG switches.
Eva-luate providing indication of the valve
'I controllers being in manual on the.not-(Refer to Drawing 7220-E-158, Sh 54;
~y
- bypassed status indi, cation panel
Reference:
ICSB Que'stion 8)
\\
To be determined 4)
Provide a technical specification to verify every 18 months the operability of the interlock logic that controls the autooatic switchover of AFW supply froo the condensate storage tank to-the service water supply system.
(Refarence:
ICSB Question 8) 5)
Meet with NRC to discuss conforoance To be determined to Regulatory Guide 1.97, Rev 2, and include status of instruoentation to detect inadequate core cooling (reactor coolant hot leg level and incore thermocouple temperature instruoent-ation;
Reference:
ICSB Question 21) 6)
Provide response to IE Bulletin 79-27 2/15/82 i
(
Reference:
ICSB Question 33)
S S
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Action Date Due 7)
Complete response to FSAR Question 2/15/82 31.54 regarding reference leg te pera-ture error effects on instru=ent accur-acy
(
Reference:
ICSB Question 35) 8)
Evaluate those components actuated 2/15/82 by ECCAS to de termine if all compo-nents on each test pushbutton can be actuated at power; for those compo-nents that are not 100% tested at power, include reference and justifi-cation in FSAR Table 7.3-6 (
Reference:
ICSB Question 36) 9)
Provide in FSAR Section 7.6 or 7.7 2/15/82 a description of the heat tracing used for the service wa ter flow transmitter, borated water storage tank level transmitter, and emer-s gency boration system when heat
. tracing design is compIlete
(
Reference:
ICSB Question 40)
- 10) Provide the design basis for the 5%
2/15'/82 flux trip and when this 5% trip is re-quired.
(
Reference:
ICSB Q9estion 43) t
- 11) Update FSAR Tables 7.4-1, 7.4-2, 2/15/82 and 7.4-3 to reference P6 ids and actual valve numbers (handwritten copy provided during m.eeting;
Reference:
ICSB Question 45)
- 12) Revise FSAR Subsection 15.1.3 to clari-2/15/82 fy that a pressure regulator malfunc-tion of 128% flow bounds a fault in the process steam transfer system.
(Refe rence :
ICSB Question 50) t 13)
In FSAR Tables 1.7-16, 1.7-17, 1.7-18.-
2/15/82 1.7-19, 1.7-20, and 1.7-21 provide a cross-reference from B&W drawing number
. to Bechtel vendor print number
(
Reference:
ICSB Question 63)
- 14) Provide a list of non-Class 1E control signals that provide input to Class IE control circuits t