ML20127M599
| ML20127M599 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/01/1985 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2284, NUDOCS 8505230313 | |
| Download: ML20127M599 (27) | |
Text
TDR 6 613 86 CERTIFIED COPY i
DATE ISSUED: May 2,1985 P
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SUMMARY
AND MINUTES OF THE p FEBRUARY 20-21, 1985 MEETING OF THE ACRS b SUBCOMMITTEE ON NINE MILE POINT UNIT 2 SYRACUSE, N.Y.
Purpose:
The ACRS subcommittee on Nine Mile Point Unit 2 visited Nine Male Point Nuclear Station, Unit No. 2 and it's support facilities on the morning o'- February 20, 1985, then met on February 20-21, 1985 at the Hotel Syracuse, 500 South Warren Street, Syracuse, N.Y., 13202. The visit and meeting were held to begin review of the Niagara Mohawk Power Corporation's (NMPC's) application for an operating license for Nine Mile Point Nuclear Station, Unit No. 2.
Notices of the meeting, published in the Federal Register on Friday, January 25, 1985 and on Thursday, February 14, 1985, are reproduced and shown in Attachment A. The schedule for the meeting as Attachment B. Sign-in sheets of meeting attendees are contained in Attachment C. Attachment D contains a list of meeting handouts kept with the office copy of these minutes.
That portion of the meeting which covered plant security was closed. There were no oral or written comments from members of the public. Mr. John McKinley and Mr. John Schiffgens were the assigned ACRS staff members for the meeting.
Attendees:
ACRS NRC Staff A. Schwencer, LB-2 C. P. Siess, Chairman J. C. Ebersole, Member E. J. Weinkam, LB-2 J. C. McKinley, Staff S. Collins, REG I J. O. Schiffgens, Staff R. A. Gramm, REG I R. A. Benedict, DHFS NMPC J. C. Lane, CSB N. Rademacher S. D. Hudson, REG I D. Pike C. D. Terry Others D. Pracht P. C. Yin, CE R. B. Abbott M. K. Allen, SWEC D. W. Barcomb M. S. Stochnoff, SWEC E. W. Leach C. Zappile, SWEC
- R. L. Raymond M. Durka, SWEC ,
W. L. Drews K. Tsang, SWEC B. Ebbeson, SWEC R. E. McCue 8505230313 850501 PDR ACRS
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IUMMARY & MINUTES /NMP-2 I'ebrurry 20-21,1985
- NMPC Others G.-E. Moyer D. A. Boe, SWEC M. J. Colomb W. L. McCoy, RGhE W. H. Wambsgan G. Wrobel, RG&E S. R. Bunyon M. Van, NYSEG C. Beckham R. Kubinak, LILCO R. B. Burtch S. C. Millspaugh, CH D. M. Cienava M. J. Wetterhahn, C&W D. R. Palmer K. Tompkins, Post-Stand M. A. Silliman (consultant) E. T. Eilmann, Duq-LCO D. A. Cifonelli C. E. Ewing, Duq-LCO G. J. Gresock P. Brostrom, Duq-LCO J. J. Bebko R. W. Fedin, Duq-LCO S. W. Wilc ek R. H. Pinney, SWEC M. A. Dool ey H. R. Peffer, GE K. F. Zollitsch R. A. Sprague, Duq-LCO R. V. Pasternak J. M. Sasaln, Duq-LCO A. G. Vierling J. B. E11mers, NYPA J. P. Thomas B. Gerbin, Francis-AVS K. D. Ward D. J. Robare, GE K. W. Korc: K. Troxley, Duq-LCO E. R. Kl ei n J. J. DeSantis, NYPSC C. L. Stuart H. R. Prins, NYPSC P. Vol:a Diane Pike, public T. J. Perkins M. D. Jones J. R. Corcoran C. V. Mangan T. E. Lempges Meetina Hiohlichts. Aareements. and Reauests:
- 4. Mr. Weinkam (NRC) briefly reviewed the history of Nine Male Point Nuclear Station, Unit No. 2 (NMP-2), discussed the status of the review, and made a brief comparison with some other similar facilities (see Attachment E).
With regard to B of the 18 Outstanding Issues, the NRC staff was still in the process of evaluating inf ormation recently supplied by the NMPC staff. Five of the Outstanding Issues were discussed during the course of the MPC presentation. The remaining 5 Outstanding Issues discussed briefly by Mr. Weinkam are as follows:
- a. Snow Loads.
In the applicant's original documentation of design in the FSAR a "100-year recurrence" snow load of 85 psf and an " extreme" snow load of 141 psf were usrd for the analysis. These were subsequently revised to ~~
a "100-year recurrence" snow load of 45 psf with no consideration of " extreme" snow load.
The NRC Staff requests that the applicant justify the
SUMMARY
& MINUTES /NMP-2 P4brurry. 20-21,1985 e
change and demonstrate that the Category I structures can withstand these snow loads.
- b. Separation Criteria.
The NRC staff has identified what appear to be inconsistencies between the applicant's stated electrical separation criteria at NMP-2. The staff requests that the applicant identify all exceptions ,
taken to the criteria contained in IEEE Standard 384 or RG 1.75 and provide suitable justification and, in particular, clarify when and where analysis is used to justify less than the required 6 in. separation in the PGCC (Power Generation Control Complex) cabinets.
- c. Safe and Alternate Shutdown.
The NRC staff is reviewing additional information on saf e and al ter 7 ate shutdown capabilities.
- d. Essential Lighting.
The applicant was asked to provide information on how adequate lighting would be meintained in plant safety-related areas other than those covered by the emergency lighting system. The applicant has stated that all actions necessary to safely shut down the plant f ollowing any design event can be accomplished from the control room and/or other areas covered by emergency lighting. The staff has yot to verify this.
The applicant was also asked to show how he would maintain adequate lighting for access to safety-related areas required for safe shutdown for longer than 8 hr. after the design-basis' seismic event with attendant LOOP.
- e. Air Start, Systems.
The Divisions 1 and 11 diesel generator air-start systems do not include air dryers. The NRC staff has reviewed the applicant's rationale for not providing air dryers and has concluded that it is not acceptable. The applicant had stated that the use of moisture separators and filters, in conjunction with manual blowdown of the air receivers and system piping will preclude any air-start system The contamination, hence, the need f or air dryers.
staff contends that the air-start system as designed for NMP-2 can not preclude corrosion and buildup of corrosion products within the system, thus subjecting the air-start system to potential contamination and **
failure to perform its safety function. The staff study of NUREG/CR-0660 has identified moisture in air-start systems as the single greatest cause of TUMMARY &' MINUTES /NMP-2 Februtry 20-21,1985 diesel generator unreliability.
The applicant announced that they have decided not to contest the issue; they will install the air dryers.
They noted, however, that they have no air dryers on NMP-1 and have had no air-start problems.
The 8 Outstanding Issues that have just become confirmatory or are still under review by the NRC staff are as follows:
- a. RWCU (Reactor Water Cleanup) Line Break (confirmatory)
- b. Preservice Inspection / Inservice Inspection
- c. Equipment Dualification
- d. Containment Fracture Toughness
- e. Post-Accident Monitoring Instrumentation
- f. Frocedures Generation Package
- g. Preoperational and Startup Test Abstracts
- h. DCRDR (Detailed Control Room Design Review) and SPDS (Safety Parameter Display System)
- 5. Mr. Collins (REG I) described the process used by the licensee to mon 2 tor and control construction quality, discussed the results of independent evaluations of the licensee performance, and addressed both the NRC inspection program and the Systematic Assessment of Licensee Performance (SALP) efforts conducted by Region I.
In reference to a recent news release (see Attachment F)
Mr. Stess asked Mr. Collins if he knew why the Regional Administrators included the Nine Mile Point plant among the most troublesome facilities to the day-to-day regulators. Mr. Collins said he could not speak for the Regsonal Administrators, however, Region I finds the current construction quality program to be generally acceptable. Recent inspection activities continue to
! identify problems and the licensee will have to institute corrective actions in response to these identified problems. Regicn I has an extensive list of outstanding problems for which licensee corrective actions have been instituted but remain to be verified and ultimately closed out as acceptable. The licensee has assigned experienced quality assurance and project management personnel to resolve site issues. Region I will monitor the remaining phases of construction and pre-operational activity as i
well as determine the acceptability of previously installed hardware to ensure the regulatory requirements .
are fulfilled.
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- 6. Mr. Mangan described Niagara Mohawk's 30 years of nuclear l
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SpMMARY & MINUTE 3/NMP-2 Ocbrutry 20-21,1985 experience, and their 15 years of operating experience with NMP-1.
- 7. Mr. Hooten introduced his staff and their tasks saying that they were prepared to go from the construction phase to the start up and test phase.
Mr. Perry described the Quality Assurance Department, staff, and experience. He discussed the NMPC assessment of contractors
- QA program effectiveness and actions initiated by contractors.and site project management to increase QA programs effectiveness on the project. He said he does not think NMPC has a la ge scale QA problem.
- 8. The function and makeup of the Safety Review and Audit of Operations organization was presented by Mr. Stuart.
With regard to the Outstanding Issue " Operations Management", potential solutions to 5 of the 6 items of concern to the NRC staff have been submitted for review.
- 9. Mr. Lompges talked about NMPC's industry interactions. He mentioned LSat they had about 40 people involved in various industry groups and emphasized their INPO participation. The INPO construction audit for NMP-2, which will be reviewed by REG I, has not yet been released.
- 10. An overview of operations staffing and training was given by Mr. Abbott. He pointed out that NMP-2 will make use of experienced personnel from startup and operation of Fitzpatrick and NMP-1; auxiliary cperators will have also been licensed on NMP-1. He presented qualification summaries for Operations _ Department Supervisors and Station Shift Supervisors (see Attachment G). He also described the NMPC general employee, chemistry /
radiochemistry technician, non-licensed operator, and licensed operator training programs. He mentioned that the success rate for SRO and RO candidates who take the test is 92 percent.
Mr. Ebersale asked if in the course of the training program they teach their operators how, for ex ampl e, an ATWS can happen, as well as an appropriate response. Mr.
Abbott said that part of the training program is to show the operators how they can get into an accident situation and what they should do'to get out of it. .
- 11. A development schedule f or Emergency Operating Procedures was presented by Mr. Colomb.
SUMMARY
& MINUTES /NMP-2 ,
Februrry 20-21,1985 l f
- 12. Rather than a NMPC staff presentation on Seismic Design ,
and_ Geology, Mr. Siess asked about seismic margins f or l NMP-2.
- 13. . Mr. Pike discuss AC/DC Power Systems and'their reli abil i ty. NMP-2 is provided with 2 independent 115 kV <
power sources and is tied to'the New York State grid
- system which is-itself tied via 26 entries to the New England grid, the Pennsylvania-New Jersey-Maryland grid, and' Canada. .The 115 kV lines are fault protected by primary and back-up schemes f ed f rom separate station
! - batteries. Offsite source A (B) normally feeds RSS 4 transformer A (B) and the auxiliary boiler transformer (there is a separate transformer for the auxiliary boil er) . A feeds one 13.8 kV bus (B the other) and the C - auxiliary boiler bus.
Various.onsite AC power systems reliability features were discussed. Mr. Pike pointed out that.there are 3
- independent divisions of safety related power, each division has a dedicated 4160 V~ bus, and each division has
^ diesel-generator to provide power under loss of offsite power or degraded voltage conditions. There are three divisions of DC power corresponding to AC power divisions, i each division has-its own battery and two 100 percent redundant battery chargers, each battery charger can supply all non-UPS loads and recharge a battery within 24 hr., and each battery can supply the worst-case DC load profile f or 2 hr. with loss of battery chargers (the batteries have and over-voltage trip).
- 14. An overview. of systems interaction was presented by Mr.
Terry. He said that systems interaction has not been evaluated in a f ormal study but was considered in virtually all aspects of NMP-2 design. He defined three
- types of system interactions considered; a) functional interactions involving interconnected systems (Limited
' PRA, Failure Modes and Effects Analysis, Evaluation of Control Systems Failures, Fire Hazard and Safe Shutdown Analysis, etc.), b) spati al interactions (High -and Moderate- Energy Line Break Evaluations, Control System
<- Failures -due to the former , Heavy Loads Evaluation, Equipment Qualification, etc.), and c) Human Interactions
' including man / machine interface and information '
interpretation (Involvement'of operation plant personnel
in review of Design Layouts, Human Factors Control Room Design Review,-and Control Room Panel mock ups during .
conceptual ' design) .
.' 15. Mr. Terry discussed the NMP-2 Decay Heat Removal Systems 4 (RCIC, RHR, HPCS, LPCS, and ADS - similar to other GE f
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SUMMARY
& MINUTES /NMP-2 Februcry 20-21,1985 He noted that NMPC BWR/5s) and design enhancements.
specified 1.15 service factors for RHR and LPCS pump motors, whereas the NSSS supplier normally provides pumps with service factors of only 1.1. The NMP-2 containment design is larger than the traditional Mark II design. He also described the physical separation criteria f or the Decay Heat Removal Systems ( see Attachment H).
- 16. Unique features of the NMP-2 Mark II containment were described by Mr. Klein. He said the stainless steel downtomers were " free-hanging", i.e., they have no bottom end bracing. Their analysis showed that the bracing was unnecessary,taking up valuable water space. Mr.
Ebersole asked what would happen if a pipe were to break and result in suppression pool by-pass. Mr. Klein responded that they were designed, with a large safety factor, not to break; e.g., they can absorb a 9-in.
deflection at the bottom without cracking. Mr. Klein pointed out that the vacuum breakers were located above the drywell floor to avoid " chucking". He also mentioned that the vacuum breakers themselves were modified for better closure.
Mr. Rademacher discussed the containment related Outstanding Issues: a) Steam By-pass of the Suppression Pool, b) Secondary Containment By-pass Leakage, c) Containment Isolation, and d) Containment Leak Testing.
The NRC staff has recently made item a) confirmatory; NMPC is to submit additional informationWith in March which the regard to item b),
staff thinks will be acceptable.
the applicant has been asked to provide additional information to justify the by-pass leakage path barriers that are relied upon to preclude by-pass flow. The applicant has provided inf ormation to justif y exemptions to some of the GDC requirements concerning c) Containment Isolation; the staff considers the information supplied insufficient. Item d) has to do with the applicant supplying adequate justification for substituting Type-A tests for Type-C tests, the latter being more stringent, i.e., having a lower acceptance criteria.
- 17. Mr. Pike talked about instrumentation f or detecting inadequate core cooling and described the NMP-2 water level measurement system (conclusive indication of inadequate core cooling). A PRA was performed on a generic plant model to put problems and potential improvements into perspective. An analysis showed that
- for a worst-case reference leg failure coupled with ,
additional single instrument failure, the core remains covered without operator action. In response to Mr.
Ebersole's question concerning possible water over-fill,
l l
SUMMARY
L MINUTES /NMP-2 F2brucry 20-21,1985 Mr. Pike said that they had analyzed their steam lines and they can withstand a full water load.
- 18. Mr. Rademacher discussed ATWS. He said NMP-2 was in conformance with 10 CFR 50.62; they are installing an
- alternate rod insertion subsystem, a recirculation pump trip subsystem, and an automatically initiated standby liquid control system which provides 86 gpm equivalent of 13 wt. percent boron. They have a back-up of 2 extra charges of baron (1500 lb. per charge) in case of wash-out. Mr. Rademacher also talked about their efforts tc.
minimize scrams through improved equipmeret and system design, and better prepared operating personnel and surveillance test procedures, noting that inadvertent actions by personnel during surveillance testing are the primary cause of unnecessary scrams. He sighted their e:<perience at NMP-1 in reducing unnecessary scrams:
Between 1972 and 1984 they averaged 3.25 scrams per year and over the past 5 years they have averaged 1.4 scrams per year (the industry average is 6.4 per year).
Mr. Ebersole pointed out that by placing valves in series on the discharge dump volume to prevent leakage they have doubled the probability of failure to open causing an ATWS.
- 19. A description of the NMP-2 Fire Protection Program was provided by Mr. Raymond. He discussed the control building and reactor building electrical separation.
- 20. Mr. Pike summarized the history of Control Room Design Review (CRDR) and described various Control Room Human Factors Design Review features, such as integrating SPDS into the review process, reviewing the remote shutdown panel, and reviewing the TSC and EOF layout. SPDS is to aid operators in determining the safety status of the plant; all operators procedures call for training without reliance on the computer.
Accident scenarios for Control Room Habitability (CRH) l were discussed by Mr. Pike, as well as CRH design features and HVAC system considerations. Mr. Siess asked if NMP-2
(
l operators are trained to function with an emergency breathing apparatus on. Mr. Pike said they did not think there was a need for such training.
l Mr. Pike said that the Remote Shutdown Panels fulfill all -
Appendix R requirements when coupled with some local ,
operations. He said that the Panels are seismically qualified, in positive pressure rooms, separated by three hour fire barriers, with class 1E redundant instruments i
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SUMMARY
&1 MINUTES /NMP-2 F'ebruary 20-21,1985 i
l and controls and divisional separation per RG 1.75. The rooms have HVAC systems physically separated from the main control room HVAC system.
- 21. Mr.'Volza discussed the NMP-2 Emergency Preparedness Plan, pointing out that it.is incorporated into an already existing-Emergency Preparedness Program supporting NMP-1.
NMPC has successf ully conducted three exercises of the i plan.
- 22. Mr. Rademacher described briefly a mini-PRA performed for NMP-2 by Stone and Webster to meet the NRC interim rule published in the Federal Register (45 CFR 40101). The study includes loss of offsite power, but no other external events. Mr. Siess asked if a sensitivity study
'had been done. Mr. Rademacher said no. The PRA did not incorporate uncertainties associated with components, rather an uncertainty band was "guestimated" for the results. The dominant risk contributors were found to be a) Cooling Water System failures, b) RHR hardware failures, c) Offsite Power failures, d) Emergency Diesel .
failures, and e) RCIC hardware failures. They calculated a core melt probability of 2.4 x 10-6. Mr. Siess asked if the PRA suggested any modest changes that could significantly reduce risk. Mr. Rademacher did not think so.
- 23. Mr. Fracht talked about the NMP-2 approach to the IGSCC problem. They replaced the thermal sleeve with forged 316L tuning f ork design and the recirculation piping with 316NG. They plan to meet EPRI Plant Water Chemistry Guidelines of less than .3 Micro MHO/CM. They have no plans to incorporate hydrogen water chemistry or IHSI (Induction Heat Stress Improvement) at this time.
- 24. Equipment qualification was discussed by Mr. Pike.
Qualification methods'and scope were presented. Non-saf ety-related equipment whose f ailure could jeopardize safety-related functions are included for consideration.
Mr. Siess asked if they have had any problems at NMP-1 with aging of components. Mr. Pike said they had not.
- 25. Mr. Volza talked about the NMP-2 Radiation Protection Program. He said the NMPC policy is to ensure that exposure of Station personnel, the general public, and the environment will be ALARA, and mentioned that, at INPO's request, they have formally endorsed INPO's 5 REM per year
- exposure guideline. NMPC projects much lower personnel ,
exposure levels for NMP-2 compared to NMP-1 due to new and improved design features.
_9-
SUMMARY
te MINUTES /NMP-2 Februtry 20-21,1985 si: .
CLOSED MEETING - SECURITY
- 26. NMPC representatives-discuss briefly Insider and Outsider security measures. They said their security system policy and practices were an extension of those employed at NMP-1, the key elements of which are barriers and access e
control. _ With regard to the Insider, they feel their personality check preclude the psychopath but not necessarily the determined saboteur. With regard to the Outsider, they have a tracking system (monitored by keycards and computer) for checking people in and out of designated areas. The tracking system can be audited.
They said they do go through drills on emergency shutdown scenarios based on sabotage initiators. Core melt is the only event which triggers evacuation.
Future Meetinas:
The ACRS is scheduled to review NMPC's application for an operating license for NMP-2 during the 299th ACRS meeting, March 7-9, 1985.
NOTE: A Complete transcript of the meeting is on file at the NRC Public Document Room at 1717 H St., NW., Washington, D.C. or can be obtained at cost from ACE Federal Reporter, Inc., 444 N. Capitol St., Washington, D. C. 20001, Telephone (202) 347-3700.
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' ' 3333' Federal Register / VIL 30. No. 31/ %ursday. Felsruary H sees 1 Notices TAnd 4.-OranAftonAL roa Other hgateus, . .$.: .; -N. N h - . FortheNedserEngsassory^===8 M TmAmmus DunAnoes , *,
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If tim.e permits the staff will ask the y ,.
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- 8'ar*" Condud d&e Moed[ig . - - - : - .
acciaccmc , ' me e n AdvisoryCommitteeenReester %b
,. Mr. Ridiard Cunningham. Director. Safeguarda,Subcoenmittee on IEne '
ma.eAm ie m ==
an ns a m . =sem= Division of Fuel Cycle and Material Mme Point UnN
- MeegngDne W
- =" " '" " Safety. U.S.Nedear Regulatory .. .
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, ' Commission, will serve as Chairman at he Federal Register pub!!shed en 3-;
- D*'8* s man *er a the meeting. Mr. Cunnhagham will . . , Friday, janaary 25.1985 (50 FR asce) J. 2 r a=#=1=ad motice of a meeting of the i E conduct the meetmg in a manner that will facilitate the orderly conduct of ACRS Subcommittee so Nine Mile Felse business. . - Unit 2. to be held on February ao and 21.
TAam ab.- CAnosovAscutan NUCGAR ne foUoWin8 Procedures apply to 1985,at the HotelSyracuse,500 Some -
h8ED' cede bur. man PROCEDURES Oesty public participation in the meeting. WarrenStreet Syracuse NY.%e
. starting time for the part of the meetag -
~" 1 Persons na submit writtes W hem on WM. hap cornments by sending a reproducible acciaccreacer m in, u eue c.e.iow - copy to Mr. Cunningham. Comments 1985 has been cW so Wa:J the i
^*^*** *** ** staning une tw &a pad of the mesdag must be received by Friday April 12 to be held on nursday. February 21. .;
.'"e" " '."*m 1985 to ensure consideration at the .
1985 mmains Am.m. AUeMaams 8""""' meeting.The transcript of the sneethig regarding this meeting remain the same will be kept open until Friday. May 17,~
as previous! announced. . . . .
1985 for the inclusion of written '. . Further ormation regardmg topics *
. r s. oomments. w. . .
to be discussed, whether the mee ~
%e NRC invites comments on the 2. Persons who want to make oral has been cancelled or rescheduled.
y proposed criteria provided by the task statements should inform Mr. Chairman's ruling on requesta for the ' '
x gI Cunningham in writing by Friday. Apdl force as outlined above.Commenters op o to pmmt out summents 12.1985. Statements must pertain to the I
may indicate whether they believe the and the time allotted therefor can be "
topics and durations suggested in the topic at hand.ne Chairman will rule on obtained by a prepaid telephone enM to '
requests to make oral statements. !
proposals are adequate, inadequate, or the cognizant ACRS staff member Mr.
y Opportmity for members of the pubile excessive, and why; whether there are John O. Schiffgens (telephone 302/es4-other management mechanisms (for to make wal statements, wWn de Mme 1413) between 8:15 a.m. and 5sDO pm ~ '
- e. ne EST. Persons plan'ning to atland this y P example, common hospital management abjY 9 g meeting are urged to contact the above fr practices or the State regulation of g g' M
'" named individual one or two days 4,.
i- i medicine) that NRC should be aware of ,pg['dm 5 be when setting standards. and the impact before the scheduled m p minutes. Oral statements may be advised of any changes in sla.aec.
3 q of those mechanisms on radiation safety:.and whether there are any other supplemented by detailed written statements for the record. Rulings and which snay have occurmd.
, d istues that the NRC should be aware of time allotments may be obtained by Dated: February 11.1885. . . .
.e- when considering physicians' training calling Mr. Cunningham at (301) 427- "Morton W. Uberkla. . .
g 4485 between 9 00 a.m. and 500 p.m. Assistant Ksecvure Ditooderjbr Asynd
- 4. , ji and experience criteria. A summary of the comments will be distributed to the EST on Friday. April 26,1965. Jterleir.
f ,,
ACMUI before the meeting. and will 3. At the meeting questions may be (FR Doc. 06-3790 Filed 3-13-85; Me and ,,.
l$ l also be available to the public at the == i == come van **ws i
L+ asked only by Committee members.
!' ' { meeting. or may be requested by consultants and NhC staff.
T j contacting Mr. McElroy after the meeting. .
4.%e transcript of the meetl and written comments will be avail le for Florida Power ar;d Ught Co. (Turkey Point Nuchar Generating Plant. Units 3
.I When preparing i:omments, persons inspection, and copying for a fee, at the and 4); Order Scheduling Prehearing 4 I should keep several points in mind. NRC Public Document Room.1717 H Contwance
,', i Authorization to use byproduct Street NW., Washington. DC 20555 on or
- l. :[ materials in humans for diagnosis and about May 31.1965. (Docket Nos. 50-350-Ot.A. 90-2514M.A.
, p treatment implies that the user's training 5. Seating for the public will be on a ASI.3P No.94-496-03 LA (Vessel Fles i, < is sufficient to avoid unwarfanted first come-first served basis. fledwetion)1 ,
l, ';. . radiation exposure to the physician. %e meeting will be held in February 4,1385.
! orkers. and the public, including accordance with the Atomic Energy Act Before Administrative indses:Dr. Robert Won t Patients; authorization does not connote of 1954, as amended (primarily section M. Lazo. Chainme n. Dr. 3uchard F. Cela. Dr.
I 161a). Federal Advisory Committee Act Emmeth A.Imbk.a. -
lg j schiesement of a particularlevelof ,
e dmical expertise.De public comment (Pub. L . 92-45). Executive Order 11789.* Please take aoGoe that a prehearing ig'a f. Pocess is not a voting mechanism. it is and the Commission's regulations in conference in the above-identi8ed I
, a request for information that might not Title 10. Code of Federal Regulations, procceding will be held on March as.
1 le asallable io NRC but that should be Part 7. 1985. commencing at 9.30 a.m local Table time, at a location in the greater Miami
. Corsidered during the regulatory Dated at Washington. DC, this it th day of
.i February.tsas. area to be designated at a later alais.
Pocest
'* .L ATTACHMENT A d -
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i 25, 1985 / Notices Fv=s1 Register / Vol. 50. No.17 / Frid:y. J nuary 3008 N entire aseeting wGIbe open to Probabilistic Assessment wGlhold o 8 combined meeting on February 14 and sprey valves is the Srst and onir public attendance.The agenda for 15.1963.Best Western Airport Park e j incident of that nature to have occurredsubject meeting shall be as follows: J l
. ctCallaway." Ah=1ty.the Bcensee Wednesday. February 20,1985- 8:.30 Hotel.600 SouthPrairie Street. l ;
quotes from the Commission's General Inglewood CA. el a.m. until the conclusion of busineas To the extent practical the meeting jF Ststement of Policy and Procedure for ' >
Mrsday. February 21.1965 - 8:30 a.m. wnlbe open to public attendance. t I
NRC Enforcement Actions which states until the conclusion of builness However, portions of the meeting willbe ,
that civil penalties "are considered for Severity LevelIIIviolations." N He Subcommittee wiB begin closed to discuss proprietary ;
operednglicenu review far Nine Mile information relating to the CESSAR hoensee sebmits that the Commaasion's -
policy lodicates that a civil penalty saaY Point. Probabilistic risk assessment. .
be considered appropriate for the Oral statements maybe presentedby N agenda for sub}ect meeting shan second and subsequent Severity Level members of the public with concurrence be as follows: -
of the Subcommittee Chairman; writtas H. Iss5-eJO a.m.
HIviolations of a "similat' nature. statements willbe accepted and made hrsday. F Fedootion of f.lernsee's Response and untilthe union ofbusineer avallable to the Committee. Recordings Conclusion wulbe permitted only during those' Mrday. February 25, m 94.as.
portions of the meeting when a untilthe conclusion ofbusiness De NRC staK has carefuBy reviewed the b,eensee a response and has transcript is being kept, and questions h SN=%n wm condnue &eir may be asked only by members of the mWw d CESSAR H fw a malDuhs condeded that the licensee did not Subcommittee.its consultants and Staff. Appmal apphenble to futum ants.
Provide any informatioe that was not Persons desiring to make oral The focus d eis needng win on altsady considered in determining the statements should notify the ACRS sta5 seismic risk.
significance of the violation and the Oral statements may be presented by appropriate civil penalty. Due to the fact member named below as farin advance members d thepubEc with the as practicable so that appropriate that (1) the violations was identified b7 arrangements can be made. .
concurance of tne Sukammittee the licensee's staff and promptly During the initial portion of the Chairman; written statements will be reportad. (2) causctive actions taken by the fican- wem prompt and extensive. meeting. the Sh==ittee, along with acmpted and made available to the Coramittee. Recordings will be permitted any ofits consultants who may be and (3) the licensee's adminatrative present, will exchange preliminary only during those portions of the controle provided an opportunity for meeting when a tranacsipt is being kept.
views regarding matters to be discovery of the violation prior tointitial considered during the balanceand ofquestions the may be asked only by criticality. the amount of the proposed
'~
meedag. members of the Sh==tttees, their civil penalty was reduced by 50% consultants, and Staff. Persons desiring The Suknmmittee wul thenhaar However. further mitigation of good performance is not warranted.
on the baale presentations by andhold todisc make=afana oral statements should notify with representatives of the NRC StaH. the ACRS staff member named below as
' Even though the licensee is correct in their annaultants, and other Interestad far in advance as practicable se that stating that a specific incident involving containment sprey valvve had not persons regarding this review. appropriate arrangementa can be made.
Further informstlan regarding topics Dwing the initial portion of the occmrod previoasty,in view of the abort to be discussed, whethat the meetir.a meeting, the Wmmittees, aloes with operating experience of the licensee, has been canceBed or rescheduled,b conclusions regarding the licenses *a any of their consultants who maybe 4 Chairman's ruling on requesta for the present, will exchange pretf=Inary good performance an difficult to resa.
,. opportunity to present oral statements views regarding matters to be Although the Enforcement Policy allows and the time allotted therefore can be considered during the balance of the -
complete mitigation on the basis of good obtained by a prepaid telephone call to meeting.
performance and for mitigation becevee the cogntran' ACRS staN member.Mr.
of presept reportang and exianalve b Subcommsittees will then home corrective notaana, the NRC etaf John O. Sdiffsens (talephone 202/e34 presentations by and hold th===<=a
'
- 1413) between 8:13 a.ra, and 500 p.nh. ' with representatives of the General believes that a civil penalty le EST. Parsons planalog to attend this
- warranted for this potentiaDy strew =rit Electric Company, the NRC StaN. their meeting are urged to contact the above cansultants, and other invited persons
.evest le eaWaba needs to be cognizant of plant that the licenses namedindividoal one or two days resarding this review.
before the scheduled mee tobe Further information about topics to be conditions and te pay greeter attentica advised of any chanaes in at Ma etc., discussed, whether the meeting has to deAails, particularly during early which may have occurred.
operati<m of the facihty.hrefore, been canceHed or macheduled, the further mitigation of the proposed civil Date lemmary tr.seen, .
Chairman's rullag oc requesta for
%um penalty is not warranted.
[TR SSitar1 %d t-24-44; 8L48 am) hsistant Execouve Directorfor hofoct h al(ted herefor pho U 85-1986 Md 1-24-46; 8.43 am) g g ,
' [TR Richard Major or Dr. Richard Sevio -
- . **28'8 88 "****'
(telephone 202/e34-32671 between ets
' W Comattese on Reactor a.m. and 5:00 p.m EST. Persone .
l*
saf*evards,sutioommittee on pehme gne poeng uma 2;IsosenS W Comdtoe en Reac9er planning to attend this aweting are Safeguards, Combined Secowwdtoes urged to contact the above maswd ,
en Gooser 5 and Renahmty and individual one or two days before the N ACRS hhr=== lues on Nine Protietsmes W toeeeng scheduled meeting to be advised of any Mile Point IJa6a 2 will hold a meeting om l
Felseery as and 21.1965. Ho6el *
- changes la schedule, etc., which may N ACRSSid>committeeson have occurnd, Syramas, nos Seamh Wanna Sueet. . CESSARIl and Haliability and g 8sensuse.NY.
- ATTACICIENT A-2 i .
~ ' - ' - - - - _ _ _ ,, _ ""-m-___,,,,.,
ATTACHMENT C'!
. .... . , Februrry 19,1985 PROPOSED SCHEDULE FOR THE FEBRUARY 20-21, 1985 kft i*'
SITE VISIT AND MEETING OF THE ACRS SUBCOMMITTEE ON {, ~ '
NINE MILE POINT NUCLEAR STATIDN, UNIT NO.2 -
FOR OPERATING LICENSE ~ REVIEW .
ac
- I Wednesday: February 20, 1985 6:15am Buffet Breakfast .
Site Visit - Plant Tour
- 1. Leave Hotel Syracuse for Plant Site 60 min
.7:00
- a. Introduction and Orientation (on bus) *
- b. Plant description (Principal Design Features)
- 2. Plant Tour (f orm 2 groups) 180 min 0:00 11:00 3. Leave Plant Site for Hotel Syracuse 60 min 12:00 - Lunch - 75 min Subcommittee Meetina - OL Review 1:15pm Opening Statements 15 min NRC Staff Presentation 1:30 4. Open Items 60 min
- a. In Particular -
Snow Loads Separation Criteria Safe and Alternate Shutdown Essential Lighting Air Start System l
I 2:30 5. Regional Evaluation of Construction ,
Issues 15 min' l
2:45 - Break - 15 min Utility Staff Presentation 3:00 6. Management Philosophy 15 min 3:15 7. Organization and Management 45 min
- a. Corporate Organization
- b. Nuclear Quality Assurance Organization ATTAGPEMT B
- . . . . .. ........ ..,,......... ................ ..... ......- .... . w ..-.....- -
l i
\
'~'
Safety Review Committee 3- 25 min
, . C OO O.
- a. Open Item - Operations Management . ,
.5 min
~4:25 9. Industry Interactions Operations Staffing and Training 30 min 4:30 10. * .
- a. Simulator ,
- b. Experience with Fitzpatrick and NMP-1 .
~
l
.5:00 - Recess -
Thursday: February 21, 1985 Subcommittee Meetino - OL Review Emergency Operating procedures 30 min C:30am 11.
Seismic Design and Geology 15 min 9:00 12.
- a. Seismic Margins
- b. Liquefaction of Dikes AC/DC Power Systems Reliability 20 min 9:15 13.
- b. Off-site Power Supply System Systems Interactions 30 min 9:35 14.
- Break - 15 min 10:05-Decay Heat Removal 40 min 10:20 15.
Mark II Containment - Unique Features 40 min 11:00 16.
- a. Open Items -
Steam Bypass of Suppression Pool Secondary Containment Bypass Leakage Containment Isolation Containment Leak Testing 11:40 17. Instrumentation for Detecting Inadequate .
Core Cooling 20 min Anticipated Transient Without Scram 30 min 12:00 18.
- a. Scram Systems
- b. Scram Reduction Efforts
- Lunch - 60 min 12:30
- 19. Fire Protection 15 min 1:30pm ATTAC!WENT B-2
1:C5
- ,,. 20. Control Room 30 min
- a. Control Room Design Review - Description
- of Power. Generation Control Complex ,
- c. Control Room Habitability 3 6 " "~
- d. ' Remote Shutdown Capability' '- .6 2:15 21. Emergency Planning . 15 min 15 min i 2:30 - Break - f 2:45 22. NMP-2 Probabilistic Risk Assessment 30 min
- a. Scope of Study
- b. What was learned
- c. How will the PRA be used 3:15 23. Intergranular Stress Corrosion Cracking 15 min 3:30 24. Environmental Dualification of Equipment 15 min 3:45 25. Radiation Protection Program 15 min 4:00 26. Plant Security (this portion of the 45 min meetino may be closed)
- a. Overview of Physical Security Plan
- b. Design Features Incorporated to Prevent Sabotage 4:45 Summary Comments: C.P. Siess 15 min
- a. Dutline NMP-2 Schedule for the March ACRS Meeting 5:00 - Adjourn -
ATTAQUENT B-3
F ACRS SUSCOMMITTEE MEETING ON NINE MILE POINT 2 _ _ _,,
SYRACUSE, NEW YORK LOCATIO.~1:
b
. DATE: FEB. 20-21, 1985 ATTENDANCE LIST PLEASE. PRINT: _ I I
NAME AFFILIATION .
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l ACRS SUBCOMMITTEE MEETING ON NINE MILE POINT 2 _ _ ,_,
g-LOCATIO.'l: - SYRACUSE, NEW YORK M 81 DATE:. FEB. 20-21, 1985 '
ATTENDANCE LIST PLEASE PRINT:
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. ACRS SUSCOMMITTEE MEETING ON NINE MII.E POINT 2_ _ __.
SYRACUSE, NEW YORK LOCA110:1:
-DATE: ' FEB. 20-21, 1985 ATTENDANCE LIST PLEASE PRINT:
~
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ACRS SU8 COMMITTEE MEETING ON _ NINE MILE POINT 2 _ _
s
. SYRACUSE, NEW YORK LOCATIO.lg DATE: FEB. 20-21, 1985 b 1/ k
~
- ATTENDANCE LIST PLEASE PRINT:
~
NAME AFFILIATION ,
Y d u%
D s , ,e M . V6- tJYJE6
\A/,L , N G -, L.Lh GwEkbc
/Nme ddk4ed 26 6
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4 ATTACHMENT. D
^
l
- 2. NRC Region I Evaluation of Construction Quality Niagara Mohawk Slide Presentation 3.
j AVV N 3 I
' Table 1.2 Comparison of Nine Mile Point Nuclear Station, Unit 2, principal design features with other 8WR/S facilities
- f. ,
- Public Power -
- Supply Sys Design feature NMP-2 Zimmer 1 La Salle tem, Unit 2 Containment type Mark II Mark II Mark II Mark II Rated thermal power, 3323 2436 3293 3323 MWt
~
1202 830 1122 1150 Gross electrical .
output, MWe Main steam flowrate, 14.263,000 10,477,000 14,166,000 14,295,dOO lb/hr Total core flowrate, 108,500,000 78,500,000 106,500,000 108,500,000 lb/hr 1020 1020 1020 1020 System pressure, nomi-nal in steam dome, psia 8x8 8x8 8x8 8x8 Fuel lattice 764 560 764 764 Number of fuel assemblies 62 63 62 63 Number of fuel rods per fuel assembly 185 137 185 185 Number of movable control rods 251 218 251 251 Reactor vessel inside diameter, in.
72-5 69-10 72-11 72-11 Reactor vessel inside height, ft-in.
1250 1250 1250 Reactor vessel design 1250 pressure, psig 6.1875 5.38 6.75 6.75 ,,
Reactor vessel base-metal minimum wall thickness, in. .
0.125 0.125 0.125 0.125 Reactor vessel minimum cladding thickness, in.
2 2 2 Number of recirculation 2
loops ATTACIU U T E NMP-2 SER 1-14
- l Table 1.2 (Continued) .
~ '
Public Power.
Supply Sys-Design feature NMP-2 Zimmer 1 La Salle tem, Unit 2 i
Recirculation loop pipe 24 20 24 24 inside diameter, in.
Recirculation pump 47,200 32,500 47,250 47,250 flowrate, gpm ,
20 20 20 Numberofjetpumps 20 1 1 1 Number of high pressure 1 '
coolant injection (core spray) loops 1 1 1 Number of low pressure 1 core spray loops .
3 3 3 Number of low pressure 3 coolantinjectionloops 361,600 354,255 361,000 428,360 Maximum heat flux, 8tu/ft2/hr 145,100 144,032 145,208 163,234 Average heat flux, .
8tu/ft 2/hr 13.4 13.4 13.4 13.4 Maximum power per fuel rod length, kW/ft 3435 3325 3325 3435 ~
Maximum centerline fuel temperature. *F 1.24 1.24 1.24 1.24 Minimum critical power ratio 1.96 1.96 1.96 Design power peaking 1.96 ,
factor (maximum rela-tive assembly power x axial peaking factor)
O 1-15 NMP-2 $ER
"." s. r4 u, o "
u ,g .o p- ,.qn'-
2.* dTl, : '-
- , # , , , l,', .
s,s nTTacanesT e 4- -
t- 49 -
4 ~ m rec .
FAX TO: Commissioners, H Street
~*
. ALL' REGIONS (PAQs) rfueggyy.g.VED C.C.0,m rg .
,, FROM: FRANX INGRAM, OPA, HDQ g ,.
- D P,4 i $
N 0- ORRISOME PLANTS *
- 4 ,,
BY' MATT YANCEY .
WRSHlWGTON (AP) -- WHILE' DECLINING TO 0FFICIALLY RANK THE NAT -
SA-0DD.0PEPRTING ATOMIC POWER PLANTS FROM BEST TO WORST: GOVE SAFETV REGUI.ATORS LIST NUCLEAR FACILITIES IN ALABANA CALIFORNIAsNEW,'.p.
. JERSEY AND OHIO AS'THE NOST WORRIS0HE.
'M*
ADMINISTRATORS OF THE NUCLEAR REGULATORY CO
- ' 0FFICES llST THE DRVIS-BESSE PLANT IN OHIO, RANCHO SECO IN CAllFORNIA: ... '
SfiLEH IN NEW JERSEY AND ' BRO.WNS FERRY IN Al.RBAHA AS.THE ONES THA TROUBLE THEN 1HE HOST.
THE REGIONAL. ADMINISTRATOR $, WHO HAVE THE FIELD RESPONSIBIL1TY FOR . \
ASSURING TijkT THE PLANTS ARE. BUILT AND OPERATED SAFELY, WERE ASKED BY THE COHHISSION DURING A 21/2-H00R HEETING TUESDAY TO SPECIFY + WHICH g/.
PLANTS NEEDED THE HOST REGULATORY ftTTENTION IN 1985.
P. '. '
' '3' WH11.E THE JUDGHENTS WERE SOMEWHAT SUBJECTIVEs davis BESSE. RANC -
SECfh SALEM AND BROWNS FERRY EHERGED AS THE THE HOST TR'00BLESOM .'
FAtiL} TIES T(i THE DAY-TO-DAY REGULATORS. '.. .
M.S0 COMING UNDER CElTICISH HE'RE THE NINE HILE POINT PLANT IN NEW.-
VORK, BERVEE VALLEY IN PENNSYLVANIA H,AINE YANKEEi WOLF CREEK IN KA
!v.,
AND THE SAN ONOFRE PLANT IN CAllF.0RNIA, .
ic, WHILE THE OWNERS OF ALL NINE F'LANTS ARE TAKlHG STEPS TO IMPROVE
'S*
'THEIR PERFORMANCE, THE NRC 0FFICI ALS SAID THEIR P '
( l 8'PAlWFULLY SLOW.I' i
THEJUDGHENTSWEREBASEDPARTIALLV0NEACHPLANT5SSitFETVRECORD,'.lJ., '
VAEi0llR PERSONNEL AND E0VIPHENT PROBLENS ENFORCEMENT ACTIONS l
EHFRGENCV SHUiDOWNS AND YEARLY ,SYSTENAilC ASSESSHENT OF LICENSEE -.y.m'g -
PERFORHANCE'8 REPORTS.
- [,* .
RUT THE SINGLE FACTOP. HENT10HED HOST OFTEN WAS THE ABILITY AND f.0HMITHEkT OF EACH UTILITY'S TOP OFFICERS TO MANAGE THE C0HPLEXI . ..
NitCl.E AR POWER. . . r .. . ..
^ jt'
THE TOP HALF-007EN PEOPLE IN THE C0HP ANY MAKE THE WHOLE -
DIFFERENCFe l' SAID JACK H6RilHe ADHINISTRATOR OF THE C0HH1SS10N'S ' ' h..l-RF010NV0FFICEHEARSANFRANCISCO.THEIRABILITYANDWill.lHGNE J'
. BF AFliTAlly SELF-CRITICAL ... AND TO C0HHUNICATE EXPECTA i'<
PEOPl.E WHQ ACTUAll.Y RUN THE PLANT ARE THE KEV' ISSUES.88 i
.4 ,AP,-WX-01-30-35 1026EST . ..
$: v C/R Distribution: Chm, Cmrs.
fN
- '. . i "d /
PE. GC, CA. ACRS. Historian, -'
h M'k f h. SECY. Records.
s n .
ORGANIZATION AND STAFFING -
Nine Mile Point 2 Operations Dept. Supervision Qualification Summary Experience Years Total Current Power Total BWR Previous License (s) License Plant Nuclear Commercial Degree Name 13 13 13 B.S.
M. Jones RO NMP1 SRO NMP1 Supv. Ops.
[3 Asst. supv. ops. RO JAF 3 SRO JAF E H
SRO JAF 7 7 4 B.S.
O. Henderson -
Supv. Radweste 3 3 3 -
M. Bullis -
Asst. Supv. Radwsste
- M V NIAGARN Si n U MOHAWK
!i, .
ale H
3
- l i
j -
- r ' -
l '
l .-
4 .
ORGANIZATION AND STAFFING ,
Nine Mile Point Unit 2 Station Shift Supervisors Qualification Summary , -
Experience Years Total Current Power Total BWR '
Previous Degree Name License (s) License Plant Nuclear Commercial 14 14 10 A.A.S.
SRO JAF '
16.5 14.5 14.5 A.A.S.
M. Colomb RO JAF SRO NMP1 16.5 16.5 10.S A.A.S.
W. Davey RO JAF SRO NMP1 9 9 9 A. A.S./ B. A.
A. Degracia - RO NMP1 SRO NMP1 16 16- 16 -
RO JAF J. Kibbe 26 -26 10 A.A.S.
G. Moyer SRO JAF SRO NMP1 SRO NMP1 9 9 9 -
J. Poindexter RO NMP1 7.5 7.5 7.5 B.S.
- . . _ - . P.E.
E. Townsend RO JAF
- M Y NIAGARA I ! R U MOHAWK
?
! l ~
I i
l
j- .
,t
}
! ORGANIZATION AND STAFFING Nine Mile Point Unit 2 Asst. Station Shif t Supv. (STA) Qualification Summary
' Experience Years I
Total Previous Current Power Total BWR Plant Nuclear Commercial Degree l
I Name License (s) License 1.5- 1.5 1.5 B.S.
B. Boucier -
- 5 5 1 B.S.
R. Carson -
B.S.
16 16 16 A.Denny G.E. -
SRO Cert.
-~
- :- 5.5 5.5 3.5 B.S.
E.Genova
- 8.5 8.5 2.5 B.S.
J. Helker -
j
- 6.5 5.5 .5 B.E.
W. Piccirilli -
- 5.5 5.5 .5 B.S.
D. Ranalli -
- 8.0 8.0 1.0 B.S.
G. Sanford -
- 9.5 9.5 9.5 B.S.
D. Wilson -
15 Y NIAGARA R U MOHAWK e
i I
PHYSICAL SEPARATION CRITERIA FOR DECAY HEAT REMOVAL SYST l
NINE MILE POINT - UNIT 2 I g
I LOW PRESSURE CORE RHS PUMP A s.
SPRAY PUMP r l l NORTH AUXILIARY BAY "
l RHS HEAT EXCHANGER A
' REACTOR CORE ISOLATION COOLING g [
D i
I
- d SECONDARY CONTAINMENT- REACTOR BUILDING - A I
O i
PRIMARY CONTAINMENT f EL 175 !z f "
J i
V s PLAN VIEW
. 1
! \
l
- I i FLOOD TROUGHS -
I O
l
- SOUTH AUXILIARY BAY
=
0 I i Ras eUMe C I RHS HEAT EXCHANGER B MH RHS PUMP B g
3 >
i n
4.
,