ML20204D350
| ML20204D350 | |
| Person / Time | |
|---|---|
| Site: | Zimmer |
| Issue date: | 12/04/1978 |
| From: | Peltier I Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7812140261 | |
| Download: ML20204D350 (14) | |
Text
.
UNITED STATES o
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NUCLEAR REGULATORY COMMISslON 4,E
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WASHINGTON, D. C. 20555
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DEC 4 1978 l
Docket No:
50-358 l
APPLICANT: Cincinnati Gas and Electric Company FACILITY:
Zimmer Nuclear Power Station, Unit 1
SUBJECT:
ACRS SUBCOMMITTEE MEETING - ZIMMER SITE - NOVEMBER 16, 17, 1978
Background:
Prior to the Advisory Committee on Reactor Safeguards (ACRS) full commi-ttee meeting on the Zimmer Nuclear Power Station operating license appli-cation, a subcomittee of the ACRS toured the nuclear station under construction near Moscow, Ohio on November 16, 1978.
On the following day, November 17, 1978, the subcommittee met with the applicant, Cincinnati Gas and Electric Company, and the Nuclear Regulatory Commission staff in Florence, Kentucky to discuss the status of the fu'lity and the Regulatory safety review.
Since the staff had not issued its Safety Evaluation Report (SER) by the time of the meeting a draft report was provided to the ACRS and the applicant as a basis for discussion. The staff plans to issue the SER in December of 1978, prior to the full cornittee meeting to be held early in 1979.
The meeting agenda and attendance list are enclosed.
Other material used for presentation purposes can be found in the meeting transcript "In the Matter of:
Zimmer Nuclear Power Plant", dated Friday,17 November 1978.
Summary:
On November 16, 1978, the ACRS subcommittee and its consultants toured the Zimmer Nuclear Power Plant near Moscow, Ohio after being given an orientation presentation by the applicant.
On November 17, 1978, the subcommittee met with the applicant and the staff to discuss the plant status and the NRC staff's safety review. The purpose of this report is to highlight significant questions and concerns raised by the subcommittee, since the meeting transcript covers the meeting in total.
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. DEC 4 1978 l
The enclosed list of questions and concerns are ordered by discipline and not in the order that they were raised at the meeting.
- However, transcript page references are provided if more detail is desired by the reader.
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-t I. A. Peltier, Project Manager Light Water Reactors Branch NO. 1 Division of Project Management Enclosures :
As Stated cc:
See next page w
Mr. Earl A. Borgmann Vice President - Engineering The Cincinnati Gas and 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 Thomas A. Luebbers, Esq.
Mr. William J. Moran Cincinnati City Solicitor General Counsel Room 214, City Hall The Cincinnati Gas and Electric Cincinnati, Ohio 45202 Company P. O. Box 960 Mr. Stephen Schumacher Cincinnati, Ohio 45201 Miami Valley Power Project P. 0. Box 252 Mr. William G. Porter, Jr.
Dayton, Ohio 45401 Porter, Stanley, Arthur and Platt Ms. Augusta Prince, Chairperson 37 West Broad Street 601 Stanley Avenue Columbus, Ohio 43215 Cincinnati, Ohio 45226 Mr. Peter H. Forster, Vice President Energy Resources The Dayton Power and Light Company P. O. Box 1247 Dayton, Ohio 45401 J. Robert Newlin, Counsel The Dayton Power and Light Company P. O. Box 1247 Dayton, Ohio 45401 Mr. James D. Flynn Manager, Licensing Environmental Affairs The Cincinnati Gas and Electric Company P. O. Box 960 Cincinnati, Ohio 45201 Mr. J. P. Fenstermaker Senior Vice President-Operations Columbus and Southern Ohio Electric Company 215 North Front Street Columbus, Ohio 43215
ACRS SUBCOMMITTEE ITEMS NOVEMBER 17, 1978 I.
Structural Engineering A.
_ Containment Concrete Temperatures - (TR 38,42,45,152)
The subcommittee and consultant (Dr. Zudans) were interested in how the applicant determined containment concrete temperatures immediately behind the steel liner during accident conditions.
Questions were raised with regard to calculational methods, assumptions, heat transfer coefficients and liner buckling.
A consultant (Dr. Catton) raised a question with regard to heat transfer coefficients used to calculate concrete temperatures and used to calculate conservative temperatures and pressures in the drywell atmosphere.
The subcommittee indicated that it would like to discuss this matter with the staff further at a future time.
B.
Temperature Distribution in the Drywell Floor - (TR-42)
A consultant (Dr. Zudans) raised a question about temperature distribution in the dryvell floor during normal operation and accident conditions.
Cracking of the floor concrete seemed to be the major concern.
The staff should be prepared to discuss its review of this matter with the ACRS.
II. Mechanical Engineering A.
Recirculation Pipe Rupture Which Damages Control Rod Drive Lines -
(TR 14, 57, 150)
The subcommittee and consultant (Dr. Catton) raised questions about the failure of a recirculation pipe in the vicinity of the control rod drive lines.
The question had to do with pipe whip and/or jet impingement which would impair the capability to scram.
The applicant's response to this postulated event seemed to satisfy the committee and the consultant.
However, the staff should be prepared to discuss the basis for acceptance both with respect to pipe whip, jet impingment and assumptions with regard to scram with disabled rod drives, in case the question comes up again (or the assumptions are not correct).
?
. B.
Long Steam Downcomers - (TR-14,133,154)
The subcommittee and a consultant (Dr. Catton) raised a question about the 36 foot long, unsupported steam vent downcomers from the drywell to the suppression pool and their ability to accommo-date lateral loads during accident conditions.
The applicant addressed this subject but the subcommittee indicated they may want more discussion at a later date.
C.
Reactor Vessel Supports - (TR-14)
Dr. Plesset was interested in the staff's position with respect to the adequacy of reactor vessel supports to accommodate LOCA loads for BWR plants.
Since this item was listed as an outstanding issue at the time of the subconmittee meeting but has been resolved since that time, the staff should be prepared to discuss the resolution with the ACRS in the future.
D.
Pipe Whip Restraints - (TR-147)
The subcommittee and a consultant (Dr. Zudans) raised questions about the technology of pipe whip restraint design (rigid vs.
energy absorbing). The staff was asked to what extent it had reviewed this matter.
The subcomittee asked the staff to provide it with the technological basis for the design in written form before the full committee meeting.
III.
Materials Engineering A.
Stress Corrosion (TR-13,184,185, 206, 210, 211' The subcommittee and consultants (Dr. Zudans, Dr. Catton) raised questions about what has been done in Zimmer to minimize inte-granular stress corrosion. The applicant responded to these questions but it was pointed out that recent events in other BWR will necessitate additional review by the staff.
One consultant (Dr. Catton) also wanted information on thermal stress problems, particularly with the collet retainer tube.
The staff will be expected to discuss its review of this matter on Zimmer in the future.
. IV.
Reactor Systems A.
The subcommittee raised questions about the effects of an ATWS on wetwell pressure and temperature.
It was agreed that discussion of ATWS was premature since the staff and ACRS are still dealing with ATWS on a generic basis.
B.
Instruments to Follow the Course of an Accident - (TR194,195, 208)
The subcommittee is not satisfied with the status of the staff's position on instruments to follow the course of an accident for plants operating or in late stages of construction like Zimmer.
The staff can expect to be questioned on this matter further in the future.
C.
The subcomittee and a consultant (Dr. Zudans) do not understand why the staff has been sitting on this generic issue so long.
They are under the impression that decouplers have been installed on German reactors although no one seemed to know for sure.
The subcommittee suggested that the staff look into this matter and find out what the Germans are doing and why.
D.
Waterhammer - (TR 201)
A consultant (Dr. Zudans) raised a question regarding waterhammer.
He seemed to be distinguishing between waterhammer in full pipes and the phenomenon resulting from empty or partially empty pipes (i.e. closing of valves etc.).
The itaff was not specifically asked to follow up on this.
V.
Core Performance A.
PBF Fuel Tests - (TR 13,176)
The subcommittee and a consultant (Dr. Catton) expressed interest in the staff's evaluation of the recent power excursion tests in PBF.
The project manager briefed the subcommittee on the staff's assessment to date.
It does not appear, at this time, that this is a problem for Zimmer but the subcommittee will probably want to be kept informed on a generic basis.
. B.
Fuel Bundle Lift - (TR 13)
A consultant (Dr. Catton) indicated that he wanted information about the fuel bundle lift problem following an accider.+ (fuel swelling).
There was no discussion of this subject, however.
The staff should be prepared to discuss this matter.
C.
Recirculation Pipe Rupture Which Damages Control Rod Drive Lines -
TTR 14, 57,150) (See IIA above)
VI.
Containment Systems A.
Long Steam Downcomers - (TR 14,133,154) (See IIB above)
B.
Reactor Vessel Supports - (TR-14) (See IIC above)
C.
Downcomer Flanges - (TR 15,163)
The subcommittee wanted to know if the staff had a good technical basis for requiring the applicant to remove the flanges from the bottom of the downcomer.
The staff agreed to discuss this further, possibly at the San Francisco meeting.
D.
Two Isolation Valves Outside Containment - (TR 50,179,181)
The subcommittee raised questions about the staff's safety philoso-phy for permitting two isolation valves outside containment in various locations.
The staff should be prepared to discuss those cases on Zimmer.
E.
ATWS Containment Pressures and Temperatures - (TR 108)
Although the question was judge to be premature, the subcommittee was interested in the wetwell pressures and temperatures resulting from an ATWS.
F.
Annulus Pressurization - (TR 126)
The subcommittee and consultant (Dr. Catton) were interested in a report on annulus pressurization and answers to questions raised by the committee to GE at a meeting a year ago.
The subcommittee would like the staff to refer it to a report on this subject.
r
. G.
Time History of Temperature and Mass Flux in Downcomers During LOCA - (TR 155,156)
A consultant (Dr. Catton) was interested in the loading on the downcomers which he feels is dependent on temperature in the pool and mass flux.
He wants to know what the temperature is at the end of chugging.
The staff should be prepared to discuss this subject.
H.
Instruments to Follow the Course of An Accident - (TR 194, 195, 208)
(See IVB above)
VII.
Electrical Systems A.
Instruments to Follow the Course of An Accident -
?94, 195, 208) (See IVB above) 8.
Loss of Of,fsite Power Due to Flood - (TR 192)
The subcommittee raised questions about the loss of offsite power due to a flood on the Ohio River and the restoration of offsite power subsequently.
The staff should be prepared to discuss this subject further.
VIII.
Foundations and Hydrology A.
Foundation Settlerr'.t Points - (TR 143)
A consultant (Dr. Zudans) raised a question about foundations settlement measurements.
He felt the applicant should continue measurements and report them to the NRC staff.
He questioned whether or not the staff is requiring merely a single point or multiple points for relative comp &rison.
The staff should be prepared to respond to this question.
B.
Loss of Offsite Power Due to Flood - (TR 192)(See VIIB above)
IX.
Organization and Q/A A.
Firefighting Responsibility - (TR 72)
The subcommittee and a consultant (Dr. Zudans) raised questions about the transition of fire fignting responsibility from construc-tion to operation, particularly with respect to the refueling floor.
The staff should be prepared to discuss this matter.
. B.
Quality Assurance Organization - (TR 74)
The subconaittee raised the question as to whether or not the staff had reviewed the QA organization changes that have taken place since its review.
The staff should be prepared to respond to this question.
C.
Industrial Security - (TR 80)
The subcommittee indicated that it would have a closed session on Industrial Security.
One particular item of interest will be security across State boarders.
D.
Relationship _Between AE and Constructor - (TR 93, 94)
The subcommittee and a consultant (Dr. Zudans) rai ed questions about the relationship of the AE (Sargent & Lundy) and the constructor (Kaiser Engineers) with respect to Q/A.
Questions such as:
Does designer get to approve design after it is installed?
Who has ultimate responsibility for component operating as designed?
How does the Zimmer arrangement compare with other arrangements the staff has reviewed?
The staff should be prepared to discuss this matter.
Revised 11/8/?8 TENTATIVE PRESENTATION SCHEDULE
)
ZIMMER SUBCOMMITTEE MEETING AND SITE TOUR CINCINNATI, OH NOVEMBER 16-17, 1978 NOVEMBER 16, 1978 Lunch and Tour Briefing at the Zimmer Site 12:30 p - 1:00 p Site Tour 1:00 p - 3:00 p Return to Holiday Inr.
3:00 p - 4:00 p NOVEMBER 17, 1978 I.
Executive Session (ACRS - OPEN) 8:30 a - 8:45 a II.
Introduction and Summary of Issues (NRC Staff) 8:45 a - 9:00 a III. Presentation by Applicant a)
Introduction, Organizational and Operational Plans for the Facility 9:00 a - 9:10 a
- organization Applicant's schedule for completion of construction 5)
Plant Description with Emphasis on 9:10 a - 9:30 a Mark II Containment Features brief description, location, and layout of the Zimmer plant c) Training Programs, Emergency Planning, and Quality Assurance and Control Programs 9:30 a - 9:50 a d)
Industrial Security Discussions (OPEN) 9:50 a - 10:00 a e) Quality Assurance / Quality Control Experience for the Zimmer plant 10:00 a - 10:15 a I
IV. Discussion of Outstanding Issues and NRC Staff Conclusion (Excluding Mark II Containment in Item VI)
(NRC Staff) 10:15 a - 11:00 a V.
Applicant Response to Item IV 11:00 a - 12:15 p 4
. {
VI.
Status of Mark II Containment Issues 12:15 p - 1:00 p (Applicant and NRC Staff)
LUNCH 1:00 p - 2:00 p VII. Status of Actions on ACRS Generic Items.
2:00 p - 2:30 p These discussions should address stress corrosion cracking, ATWS, loss of on-site and off-site alternating current / reliability of direct current power systems, instruments to follow the course of the accident, recir-culation pump overspeed during a LOCA, loose parts monitoring, and vibration monitoring.
(Applicant and NRC Staff)
VIII.
Executive Session (ACRS - OPEN) 2:30 p - 2:45 p IX.
Presentation by Members of the Public as 2:45 p - close of requested (Interested Members are Requested business to Contact S. Duraiswamy or R. Savio at 202-634-3267)
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