ML17054A126
| ML17054A126 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/20/1983 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Rhode G NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 8310050131 | |
| Download: ML17054A126 (12) | |
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>983 Docket No.:
50-410 Mr. Geral~l'K.
Rhode Senior Vice Pr esident Niagara Mohawk Power Corporation 300 Erie Boulevard i<est Sy'raouse, New York 13202
Dear Mr. Rhode:
DISTRIBUTION:
~Document Control NRC PDR Local PDR NSIC PRC LB¹2 File EHylton MHaughey
- ELJordan, DEQA:IE
Subject:
Nine Nile Point OL Safety Review - Request for Additional Information Ne have completed our initial review of FSAR Sections 13.5.2 and 15.8, as well as items I.C.7 and I.C.8 of FSAR Section 1.10.
Enclosure 1 identifies additional information required for our review of these areas.
Consistent with the licensing review schedule for Nine Mile Point Unit 2, responses to this request for additional information should. be submitted as changes to the FSAR by October 27, 1983.
If you have any questions concerning the enclosed request for additional information, please call the licensing project manager, Mary F. Haughey, at (301) 492-7897.
Sincerely,
~iXae'X a~ed b3/3
Enclosure:
As stated A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing cc w/ enclosure:
See next page 83i0050i3i 830920 PDR ADOCN 050004i0 A
PDR OFFICE/
SURNAME)
OATE P DL:LB¹2/PM MHaugheg: pt 9/2C/83
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- UG. GPO 1983~00-247
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Nine Mile Point 2
Mr. Gerald K. Rhode Senior Vice President Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 CC:
Mr. Troy B. Conner, Jr.,
Esq.
Conner
& Wetterhahn Suite 1050 1747, Pennsylvania
- Avenue, N.W.
Washington, D.
C.
20006 Mr. Richard Goldsmith Syracuse University College of Law E. I. White Hall Campus
- Syracuse, New York 13210 Mr. Jay Dunkleberger, Director Technological Development Programs New York State Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Ezra I. Bialik Assistant Attorney General
'nvironmental Protection Bureau New York State Department of Law 2 World Trade Center New York, New York 10047 Resident Inspector Nine Mile Point Nuclear Power Station P. 0.
Box 126
- Lycoming, Ne'w York 13093 Mr. John W. Keib, Esq.
Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202
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REQUEST FOR ADDITIONAL INFORMATION NINE NILE POINT NUCLEAR STATION, UNIT 2 OPERATING AND MAINTENANCE PROCEDURES AHD A'AIS Section 13.5 of the FSAR for Nine Nile Point, Unit 2 (NMP-2}
indicates that Niagara mohawk Power Corporation (HNPC) will conform to Regulatory Guide 1.33, but does not indicate the applicable revision number.
A commitment is also made to ANSI 18.7-1972.
The revisions to these documents that are referenced in NUREG-0800 "Standard Review Plan" are Regulatory Guide 1.33, Rev.
2 ('ebruary 1978) and ANSI/ANS 3.2-1981 (Draft),
Hodify Sections 13.'5 and 13.5.1.1 of the FSAR to commit to these revisions or provide justifi-cation for this deviation from the Standard Review Plan.
A commitment to conform to ANSI/ANS-3.2 (1982) would also be acceptable, although this version of the standard has not been formally endorsed by the NRC staff.
Section 13.5.2. of the FSAR includes a category entitled "Special Operating Procedures,"
along with a statement that these procedures are "directed'owards plant conditions."
Provide a complete. list or description of the specific plant conditions or events covered by this category of pr'ocedures.
There are inconsistencies in the titles used in Tables 13.5-1, 13.5-1a, 13.5-3, and 13.5-4.
Table 13.5-1 contains the titles "Operation Procedures" and "Special Procedures."
Table 13.5-1a contains the titles "Special Operating Procedures" and "Emergency Operating Procedures."
Table 13.5-3 contains the'title "Special or Emergency Operation."
Table 13.5-4 contains the titles "Operating" and "Special Emergency."
Section 13.5.2.1.2 states that the format and content of "Special Operating Procedures" are given in Table 13.5-4.
However, Table 13.5-4 does not include this specific title.
The above inconsistencies should be resolved.
Also, the relationship between special and emergency procedures should be clarified and.a subsection added to Section 13.5.2 to discuss Emergency Operating Procedures, if a category labelled as such is to be used.
Expand Section 13.5.2.2 "Other Operating and Haintenance Procedures" to address modification procedures.
The general objectives and characteristics of modification procedures should be described.
A list of titles of modification procedures is not required.
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Section 13.5.2.1.1, "Operating Procedures,"
provides-several examples of operating procedures.
Section" 13.5:2.1.2, "Special Operating Procedures," lists typical events included in NHPC's special operating procedures category.
Nodify these sections to list all procedures in each category, not just examples.
Coverage for the following procedures, from Appendix A to Regulatory Guide 1.33, Rev. 2, is not evident and should be incorporated into Section 13.5.2 under the appropriate categories:
NOTE:
Coverage for the procedures must be assured.
- However, the actual titles or combinations of procedures are NMPC's option.
(1)
General Plant Operating Procedures Recovery from Reactor Trip Operation at Hot Standby Turbine Startup and. Synchronization of Generator Changing Load and Load Follow (if applicable)
Power Operation and Process Honitoring Power Operation with less than Full Reactor Coolant Flow Preparation for Refueling and Refueling Equipment Operation Refueling and Core Alterations (2)
Procedures for Startup, Operation, and Shutdown of Safety-Related BNR Systems NOTE:
Provide a list of titles of the procedures in which instructions for the Starup, various modes of operation and shutdown of the following systems will be included.
Nuclear. Steam Supply System (Vessel and Recirculating System)
Reactor Cleanup System Liquid Poison System (Standby Liquid Control System}
High Pressure Coolant Injection Reactor Core Isolation Cooling System Emergency Core Cooling Systems Closed Cooling Mater System Containment (1
Maintaining Integrity
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2 Containment Ventilation System 3
Incr ting and deinerting Fuel Storage Pool Purification and Cooling System Bain Steam System (reactor vessel to turbine)
Turbine-Generator System makeup System (filtration, purification, and water transfer)
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I Service Water System Reactor Building Heating and Ventilation Systems Control Room Heating and Ventilation Systems Radwaste Building Heating and Ventilation Systems Standby Gas Treatment System Instrument Air System Electrical System
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- 1) Offsite (access circuits) 2 Onsite (a} Emergency Power Sources (e.g., diesel generator, batteries)
(b) A.C. System (c) D.C. System Nuclear Instrument System
- 1) Source Range
- 2) Intermediate Range
- 3) Power Range
- 4) TIP System Reactor Protection System Rod Worth Ninimizer Procedures for Combating Emergencies and Other Significant Events Loss of Instrument Air Loss of Electrical Power.. (and/or degraded power sources)
Loss of Core Coolant Flow Loss of Condenser Vacuum Loss of Containment Integrity Loss of Service Water Loss of Shutdown Cooling Loss of Component Cooling System and Cooling to Individual Components Loss of Feedwater or Feedwater System Failure Loss of Protective System Channel Mispositioned Control Rod or Rods (and rod drops}
Inability to Or ive Control Rods Conditions Requiring Use of Emergency Boration or Standby Liquid Control System Fuel Cladding Failure or High Activity in Reactor Coolant or Offgas Fire in Control Room or Forced Evacuation of Control Room
'urbine and Generator Trips Other Expected Transients that may be Applicable Nalfunction of Automatic Reactivity Control System
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Nalfunction of Pressure Control System Reactor Trip Plant Fires Irradiated Fuel Damage While Refueling Abnormal Releases of Radioactivity Intrusion of Demineralizer Resin Into Primary System (BWR Plants)
'n an April 14, 1983 letter from C.
V. Nangran to Darrell G. Eisenhut, NHPC committed to provide a procedures generation package (PGP).
The PGP is required by Supplement 1 to NUREG-0737.
In view of this commitment, and the member-ship of an NSSS vendor representative on the Joint Task Group (Section 14.2.2.4.1),
the staff considers TNI-2 Task Action Items I.C.7 and I.C.8 resolved.
Action Item I.C.7 is resolved because NNPC has committed (in Section 1.10 of the FSAR) to develop the PGP'ased on NRC-approved BWR Owners Group Emergency Procedure Guidelines.
Therefore, an additional NSSS vendor review of the procedures is not necessary.
Action Item I.C.8 is resolved because of NNPC's commitment to submit a PGP.
Revise FSAR Section 1.10 to provide a brief explanation of how Task Action Items I.C.7 and I.C.8 have. been resolved, as described above.
Suitable cross-reference between Sections 1.10 and 13.5.2 should be provided.
Because the PGP will provide infor-mation necessary for the staff to complete its review of Section 13.5.2, the PGP should be sent to NRC as an FSAR amendment.
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