ML20235A891
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ADVISORY COMMirTEC ON REACTOR SAFEGUARDS UNITLD STATts A*WM C ENEf6Y COMMISSION WASHING TON. D.C.
20545 September 25, 1973 l
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l ACRS Members ACRS Staff HANDL'ING OF TWO DOCUVENTS FORWARDED FROM THE ACRS OFFICE i
l It has been brought to my attention that two documents that I sent out on August 6, 1973 should have been marked Official Use only and should be handled as such. The documents are attached to my letters " Seismology in the Vicinity of the Grand Gulf Nuclear Plant" and Consultant Reports on Dynamic Behavior of Water in the Torus i
of the EWR, Mark I Pressure Suppression Containment," both dated August 6, 1973.
Please mark both the letters and the documents " Official Use Only" and handle them as such.
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J. C. McK nicy y
Senior Staff Assivuant 1
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EXCERPT FROM MINUTES OF 227TH ACRS MEETING PARCH 8-10,1979 III. Meeting on William H. Zimmer Nuclear Power station Unit 1 (OL) (Open to Public)
[ Note:
Richard P.
Savio was the Designated Federal Employee for
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this portion of the meeting.)
s A. Subcommittee Report g
i Mr. Bender, Zimmer Subcommittee Chairman, discussed the status of the Subcommittee's review of the application for an operating license for the Zimmer Nuclear Power Station, and included a site description, a sumary of the Mark II Containment lead plant load evaluation and acceptance criteria, a Mark II pool dynamic load summary, technical evaluations by ACRS consul-tents, a sumary of the Mark II Containment Reassessment Program, and inspection reports and correspondence relating to allegations of noncompliance with NRC criteria and regulations (see Appendix XII).
He noted that some questions had been raised regarding quality assurance at Zimer, but that an active program has been established to correct any of the difficulties, that the NRC Staff is monitoring this program, and at this time is satisfied.
[ Note :
J.
Flynn, Cincinnati Gas and Electric Company (CG&E) coordinated presentations for the Applicant; I. Peltier for the NRC Staff.)
B. Status of NRC Staff Review I. Peltier discussed the status of the NRC Staff's review, and noted that the review of the Zimer application has been com-pleted, and subject to satisfactory resolution of very few remain-1 ing issues, the plant may be operated without undue risk to the health and safety of the public.
(For a list of outstanding and confirmatory items, see Appendix XIII.)
J.
Schultz, NRC Staff, explained the reasori for the NRC Staff's revision of the safety evaluation report.
He said that for the past several months, the Office of the Executive Legal Director (CELD) has been concerned that an adequate basis for the conclusions presented in the SER has not been provided.
This matter was brought to the attention of the OELD by the AS&G.
The NRC Staff incorporated an improved description of the bases for the conclusions drawn in the SER, and as a result a revision was issued that concurred with the requirements set j
forth by OELD.
Approximately half of the text in the report was affected.
Most of the changes occur in two categories, the l
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.v MINUTES OF THE 227TH ACRS MEETING
' MARCH 8-10,y1979
- i citing, of approved references or. the detailed descriptions of l
the bases used in the report.
No substantive changes in the conclusions occurred as a result of this effort.
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Schultz noted that this revision problem will affect most of the plant reviews in the near_ future.
C. Applicant's Presentations j
- 1. Operating Organization E.
Borgmann, CG&E, provided an organization chart for-the operation of the Zimmer Plant (see Appendix XIV).
In answer to a question, he noted that among supervisory-personnel there is accumulated 75 man years of experience, and ' among operators there is also approximately 75 man years of experience in nuclear plants.
- 2. Plant and Site H. Brinkmann, CG&E, discussed the location and the layout of the Zimmer plant and the site upon which it is located. He noted that the site is approximately one-half mile from the village of Moscow, Ohio, and is located near the Ohio River on its flood plain. He noted that U. S. Highway 52 runs adjacent to the site, as does the Ohio River, on which there is freight barge traffic.
Using aerial photographs, he identified the major structures on the site.
He 'noted that discharged steam from the safety valves is piped through the reinforced concrete floor that separates the dry well from the wet well, and is discharged into the suppression pool through quenchers.
For 1
loss of coolant accidents, downcomers are provided to exhaust steam from the dry well to the. suppression pool.
Thirteen safety relief valves are provided.
Dr. Krishnaswamy, Sargent and Lundy, discussed the engi-neering details of the Mark II containment system.
- 3. BWR/V Changes from BWR/IV R.
Johnson, GE, discussed the differences between the BWR/V Nuclear Steam Supply System (NSSS) and the BWR/IV NSSS (see Appendix XV).
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He noted that the solid state manual control system is j
being applied for the first time at Zimmer.
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MINUTES OF THE 227TH ACRS MIETING MARCH 8-10, 1979 4'. Personnel Training J. Schott, CG&E, discussed Zimmer's initial plant staff training program, its requalification program, and its replacement training program (see Appendix XVI).
Mr. Okrent noted that since Zimmer is the first nuclear plant that the Applicant will operate, and since there is a relatively small number of personnel experienced in nuclear plant operations on board, he recommended that the Applicant appoint at least one ex-perienced person onto the Offsite Review Committee.
I. Peltier noted that the Applicant meets ANSI Standard 19.1 for both operator and supervisor personnel training.
J. Schott also provided an organization chart for the operating force at Zimmer.
D. NRC Et:ff Report On the CE Merk II Containment System C. Anderson, NRC Staff, discussed the state of the Staff's review of the Mark II Containment System, and the findings to date (see Appendix XVII).
He noted that the review is essen-tially complete, and that although not all of the documentation is complete, the NRC Staff sees no problem with licensing this containment in this plant.
He noted that the review is docu-mented in NLREG-0487.
J.
A.
Kudrick, NRC Staff, noted that since no data were i
available on Mark II, the NRC Staff used conservati ve values.
He said that the criteria will be revised when adequate new data are available.
I. Peltier said that the NRC Staff is satisfied that the Mark II containment is designed to accept pool dynamic loads.
E. General Questions J.
Kovacs, NRC Staff, said that the containment and its equipment will be evaluated on the basis of the absolute sum method of calculation.
Some components, that do not meet the criteria using absolute sum calculations, but do meet these criteria using square root of the sum of the squares calcula-tions, will be considered case by case.
Mr. Okrent requested that information be provided him regarding the capability of instrumental. ion to follow the course of an ac-cident to measure radiation levels inside containment for three pstualted events:
1)
Class-9 Accidents, 2) 10 CFR 100 Ac-.
- MINUTES OF THE 227TH ACRS M2ETING MARCH 8-10, 1979 cidents, and
- 3) a best estimate for a LOCA.
He also asked for estimated radiatien levels fer each of these events.
J.
Flynn agreed to provide this information.
Mr. Ray requested information on grid load flow and stability in CG&E's electric distribution system, and asked for a copy of the load swing curve for the most marginal case for grid operation (the slowest rate of return to stable conditions following a loss of Zimmer from the grid).
Mr. Ray also requested a diagram of CG&E's 345 kv network.
J. Flynn agreed to provide this informa-tion.
In answer to a question regarding settlement of structure, I. Peltier said that differential settlement of the base mat is not a major problem.
Differential settlement between adjacent building: shculd and will be monitored.
He noted that measure-ments made on March 1 were of the same value as those made in December.
In answer to a question, I. Peltier said that there are two separate remote shutdown panels.
'Ihese panels can be used only for shutdown.
J.
Borgmann said that CG&E believes that it has a solid power plant operating background, and that it has adequate staffing for the Zimmer plant.
CG&E has a commitment to, and will provide efficient, safe operation.
F. Caucus Members were polled, and agreed that they could try to write a report on the Zimmer Nuclear Power Station Unit 1.
Members identified items that they believed should be included in the report.
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OUTSTANDING ISSUE MARK II ACCEPTANCE CRITERIA LOAD CRITERIA DESIGN ASSESSMENT rrctirra ADVISORY C0r.M!TIEi C7 RE ACluk S A FiCU?.* *>3 tL S. l.. '
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ACRS SER DESIGNATION SUBJECT SECTION 11-1 TURBINE MISSILES 3.5 II-5A LOOSE PARTS MONITOR 4.4.1 II B-2 QUALIFICATION OF NEW FUEL 4.2 GEOMETRIES 11 B-4 STRESS CORROSION CRACKING IN 5.2 BWR PIPING II C-4 VESSEL SUPPORT STRUCTURES 5.2.1 II C-5 WATER HAMMER 6.3.2 II C-6 MAINTENANCE AND INSPECTION 12.3 0F PLANTS (VIEWGRAPH 5) l l
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COMPREHENSIVE DESCRIPTION PROVIDED IN APP H (JULY 77) l e
TO ZIMMER FSAR e
PRINCIPAL NRC REVIEW AREAS CAVITATION PROTECTION RECIRCULATION FLOW INCREASE TRANSIENT FLOW CONTROL VALVE POSITION DURING LOCA NRC REVIEW COMPLETE AND SYSTEM IS ACCEPTABLE e
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INITI AL PLANT STXF~" T"#**'h TRAINING PROGRAM B.
REQUALIFICATION PROGRAM C.
REPLACEMENT TRAINING PROGRAM
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I Af' INITIAL PLANT STAFF TRAINING PROGRAM 1.
OPERATIONS GROUP A.
INITIAL COLD LICENSE TRAINING PHASES I THRU VI a.
NONLICENSED OPERATOR TRAINING 2.
SUPERVISORY STAFF A.
INTRODUCTION TO NUCLEAR POWER B.
ACCELERATED NUCLEAR POWER PREPARATORY TRAINING
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STATION NUCLEAR ENGINEERING I
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BWR CHEMISTRY E.
BWR MAINTENANCE F.
NUCLEAR INSTRUMENTATION e.
PROCESS INSTRUMENTATION AND CONTROL H.
BWR OPERATING FUNDAMENTALS-I 1.
OBSERVATION AND TRAINING AT OPERATING FACILITIES 3.
PLANT TECHNICIANS A.
ZIMMER ORIENTATION B.
NUCLEAR FUNDAMENTALS c.
RADIATION PROTECTION p.
SPECIFIC COURSES
- 1. - ELECTRONIC FUNDAMENTALS II. - NUCLEAR INSTRUMENTATION III. - DIGITAL LAB Iv. - SYSTEMS TRAINING
- v. - GENERAL MAINTENANCE (CENTRIFUGAL PUMPS, VALVE LAPPING & PACKING, RIGGING & LIFTING, ETC.)
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PARTICIPATION IN PREOP & STARTUP TESTING: LAB & SHOP SET-UP; ON-THE-J0B IN THEIR SPECIALTY.
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APPARATUS OPERATION D.
PLANT CHANGES (DESIGN, PROCEDURES, T.S., ETC.)
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PROCEDURE REVIEW (ABNORMAL & EMERGENCY)
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PERSONNEL EMERGENCY 1.
APPLICABILITY - INDIVIDUALS WITHIN THE SITE BOUNDARY REQUIRE EMERGENCY TREATMENT B.
STATION EMERGENCY 1.
APPLICABILITY - PHYSICAL OCCURRENCE WITHIN THE PLANT, VERY UNLIKELY THAT OFFSITE HAZARDS WILL RESULT.
EXAMPLES A.
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RELEASE OF T0XIC GAS n.
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GENERAL EMERGENCY THREE CATEGORIES DIVIDED ACCORDING TO SE' VERITY, GENERAL EMERGENCY INVOLVES A RADIOACTIVE RELEASE INTO THE AIR, WATER, OR GROUND SUCH THAT INITIAL ASSESSMENT INDICATES OFFSITE AGENCY NOTIFICATION IS NECESSARY.
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NOTIFICATION - EXCEEDS REPORTABLE TECH. SPEC, VALUES-2.
MOBILIZATION ALERT -
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SHORT TERM (UP TO 24 HRS)
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SHORT TERM TO RIVER UNIDENTIFIED GROSS BETA -
GAMMA ACTIVITY CONCENTRATION >l MPC AFTER DILUTION AT THE DOWNSTREAM WATER INTAKES c.
ACTUAL OR PREDICTED OFFSITE CONTAMINATION DUE T0. STATION OPERATION FOR WHICH FRC PAG's MAY BE EXCEEDED FOR AGRICULTURAL PATHWAYS, 3.
OFFSITE GENERAL EMERGENCY ACTUAL OR IMMINENT ATMOSPHERIC RELEASES LIKELY TO RESULT IN DOSES EXCEEDING EPA PAG's.
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[MDCRITERIA
- 3. - ASYtt1ETRIC -
-EVALUATIONOFZ!mERCONTAINMENT i
POOLSWELL
-LETTERREPORT-MARCH 14,
'7" QUENCHER ARM loads UsEDFFRMETHODFORFOURARM QUENCHER 5.
"T" QUENCHER USEDFFRMETHODFORFOURARM TIE-DOWNLOADS OUENCHER 6.
"T" QUENCHER ZONE OF INFLUENCE CYLINDRICALZONEOFINFLUENCE
. os ZITHER MK 11 l.txDS i
UNDER REVIEW u
LOAD / PHENOMENA RESOLUTION
- 1. QUENCHER AIR
-6LOADCASESMEETINTENTOFNRC
.CLEARINGLOADS CRITERIA 0F SRV LO4D f%GNITUDE, FREQUENCY AND PHASING. CONFIRM' WITHIMJTESTDATA. MARCH 1979.
- IN-PLAffT CONFIRf% TORY TEST j
PLANNED.
l 2.
LOCA JET SUBMERGED DRAG
-llEWRINGVORTEXMODEL i
-PRELIMitMRYSTAFFREVIEW thRCH1979 i
3-5, LOCW SRV AIR BUBBLE DRAG
-ACCELERATIONDRAGCOEFFICIENTS
- EQUIV.' VELOCITY IN A UNIFORM FLOW FIELD.
-INTERFERENCEEFFECTSCLOSELY SPACED STRUCTURES l
- GENERIC REPORT MeRCH 1979
- 6. CHUGGING FSI
- GENERIC RESPONSE TO l4RC QUESTIONSMARCH1979
- IP CONFIRf% TION i
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1 POOL DytaMIC LoAo CONFIRt% TORY PROGRAM
- ZImER IN-PLANT IESTS
-TESTPLANlhRCH1979, 1
- EXTENDED II IESTS I
-CONDENSATIONOSCILLATIONS
-PROTOTYPICALVENTLENGTH i
i-
- REPORT f0 1980 f
t
- lhw Gifi II' - TEST PROGRAM
- CONDENSATION OSCILLATIONS
-VENTLATERALLo4DS
- PROTOTYPICAL OF A SPECIFIC PLANT
-DATA,lhY1980 1
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CONCLUSIONS ZImER POOL IMw41C LOADS
-ZIMMERADOPTEDLARGEIhJORITYOFllRCCRITERIA
- ANTICIPATE lb PROBLEMS IN RESOLVING FEw OPEN ITEMS
- ZIMER SER SUPPLEMENT bCH 1979
- GENERIC SUPPLEMENT TO IUREG 0%7 APRIL 1979
- fix 11 CONFIRt% TORY PROGRAM AND ZIMMER IN-Pvwr TESTS CONFIRM i
LEADPLANTLOADS 1
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1 h.;.N March 13, 1979 D
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tionorable Joseph M. Hendrie Chairman.
i U.S. Nuclear Regulatory Commission j
Washington, DC 20555 y
SilBJECT:
REPORT ON WILLIAM H. ZIMMER NUCLEAR POWER STATION, UNIT 1 i
l
Dear Dr. Hendrie:
j During its 227th meeting, March 8-10, 1979, the Advisory Committee on j
Reactor Safeguards completed its review of the application of the Cin-cinnati Gas and Electric Company (CG&E), the Columbus and Southern Ohio i
Electric Company, and the Dayton Power and Light Company (hereinafter referred to collectively as the Applicants) for' authorization to oper-I-
ate the William H. Zimmer Nuclear Power Station, Unit 1.
CD&E will be, i
responsible for operating the plant. A tour of the facility was made
', l by members of the Subcommittee on November 16, 1978 and the applica-t
. tion was considered at Subcommittee meetings on November 17, 1978 and l
February 77, 1979.. During its review, the Committee had the benefit of discussions 'with representatives and consultants of the Applicants,
- .i the General Electric Company, Sargent and Lundy Company,, Kaiser Engi-neers, Incorporated and the Nuclear Regulatory Commission (NRC) Staff.
.}
The Committee also had the benefit of the documents listed. Se Com-mittee reported on the application for a construction permit for this l
plant on September 17, 1971.
ij W e Zimmer Nuclear Power Station is located in Ohio on the Ohio River approximately 24 miles. southeast of Cincinnati and one-half mile north of Moscow, Ohio. We plant will utilize a 2436 MWt BWR/S boiling water l 'l reactor which is similar to the BWR/4 used in the Edwin I. Match Nuclear Plant, Unit No. 2.
A principal difference is the use of recirculation flow control valves to regulate power rather than pump speed control 4
which has been used on plants of the IMR/4 type.
l
'the Zimmer Nuclear Power Station has a Mark II pressure suppression containment and is designated as one of the lead plants for this type containment. We mC Staff has reviewed the generic aspects of the Mark II containment system and has reported its findings in NURBG-0487 '{i, m,
l' The generic aspects of Mark II load evaluation and acceptance criteria j
were considered at Subcommittee meetings on July 7-6, 1977, November 30,
.g, 1977, May 23, 1978, and November 28-30, 1978. De Committee believes' die cwveguri Ne v&ilatia wuiicab1s $6 Nm 1&M $2N II p1=ulu.
Laat s1w orracs >
l ounmassa k D'AT8
- NRC PORM 318 (9-76) NRCM 0240 W u. s. oovanmusar eneurine orpses, sete.sanoa4 h
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g j
o Honorable Joseph M. Hendrie March 13, 1979 i
4%
is.
'the Applicants have taken exception to some of the acceptance criteria M"7g' developed by the E C Staff.
%eStaffandtheApplicantsarecontinudig:;n ing to work together to resolve this matter.
WeCommitteewishestodg;
be kept informed.
9 -
he Mark II Owners Group and the NRC Staff are continuing to develop i
infonnation relating to the method of combining loads on the contain-ment structure. Ibwever, the Applicants have indicated that they will l
accept the E C Staff's current, perhaps overly conservative, methodology, to expedite the licensing action. W e Committee considers this acceptable, i'
We EC Staff has determined that the present thergency Core Cooling System analysis contains adequate margins for assessing the perfonnance i
of the Zimer Plant.
It should be noted that recent tests in the 'No Ioop Test Apparatus (TLTA) have produced new data on the rate of vapor-
)
ization of emergency core cooling water. W e M C Staff believes that I
further analysis of the 'M.TA test results may require changes in the l
General Electric model for calculation of this vaporization rate in i
order to reflect more accurately the observed physical thenomena. We i
Ccrinittee wishes to be kept informed.
In view of the important role of the Operational Review Committee in pro-j
~
viding continuing reviews, and in updating aM implementing safety meas-ures, the ACRS recwwe$s that the Operational Review Committee inclu$e additional experienced personnel. from outside the corporate structure as i
voting members for the first few years of operation.
[
With regard to the generic items cited in the Committee'si report, " Status j
of Generic Items Relating to Light Water Reactors: Report No. 6,* dated j
November 15, 1977, those items considered relevant to Zimmer are:
II-4, j
Sb, 6, 7, 8,10; IIA-4; IIB-4; IIC-1, 3A, 3B, Si IID-2. %ese items should be dealt with by the NRC Staff and the Applicants as solutions are l'
found.
We Mvisory Comittee on Reactor Safeguards believes that, if due consid-eration is given to the items mentioned above, ard subject to satisfactory j
completion of construction aM preoperational testing, the William H. Zimmer I
Nuclear Power Station, Unit 3 can be operated without uMue risk to the health and safety of the public.
Sincerely, N
ORIGID L 3:cen 3y MAX W. C1:303 1
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mairman ome n y sunnams >
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NRC PORM 318 (9 76) NRCM 026
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Honorable Joseph M. Hendrie Msrch 13, 1979 j
References:
i i
1.
Cincinnati Gas and Electric company, ' Final Safety Analysis Report, William H. Zimmer Nuclear Power Station, Unit 1,* with Wannements 23 throt 3h 82.
i 2.
U. S. Nuclear Regulatory Commission (USlRC), 'Bafety Evaluation Report i
Related to the Operation of William H. Zimmer Nuclear Power Station, Unit 1, Docket No. 50-358,* USmc Report NURD 0528, dated January 31,
-i 1979.
3.
U. S. Nuclear Regulatory Conraission, ' Mark II Containment T. mad Plant Pro 3 ram I. cad Evaluation and Acceptance Criteria," USIStC Re-port NUR5fA487, dated October,1978.
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