ML19345F201
| ML19345F201 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck, Millstone File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 02/04/1981 |
| From: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO., NORTHEAST NUCLEAR ENERGY CO. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| A01452, A1452, NUDOCS 8102090450 | |
| Download: ML19345F201 (19) | |
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NORTHEAST UTilJTIES 5
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Docket Nos. 50-213 Y
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,.JDirector of Nuclear Reactor Regulation Attn:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch #5 U. S. Nuclear Regulatory Co= mission Washington, D.C.
20555
Reference:
(1) D. G. Eisenhut letter to SEP Plant Licensees, dated January 14, 1981.
Gentlemen:
Haddam Neck Plant Millstone Nuclear Power Station, Unit No.1 Systematic Evaluation Program Redirection Connecticut Yankee Atomic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) have reviewed Reference (1) and concur that the majority of the commitments specified were discussed and agreed to in meetings between the SEP Owners and representatives of the NRC Staff. Specifically, the SEP Owners Group Program provides that:
(1) 60% of all topic assessments are to be completed by the end of June, 1981.
(2)
There be a lead plant concept to identify SEP plants responsible to work with the Staff reviewers in developing the initial topic assessments for those topics for which a topic assessment has yet to be completed. Because of long-lead characteristics or in-adequate definition of applicab?.e criteria, there is the possibility that all initial assessments may not be completed under the program by the end of June,1981; however, that should not preclude achieving the other Staff goals within that time interval.
The nine SEP Owners Group plants represent 1233 SEP topics for resolution. As of January 9, 1981 504 of those topics were identified as deferred from the SEP as a generic issue or were not applicable to the SEP. In addition, 207 8102090 N
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ii topics had draft or final SER's issued. The SEP Owners Group members vill review the draft SER's and apply the criteria and findings where possible in generating assessments of that topic for their plants. The order of business in the 90 day trial period is to first complete the draft SER's and then generate topic assessments on each of the topics where the Staff has issued a lead topic SER. It is anticipated that the draft SER's issued by the NRC by January 15, 1981 vill be reviewed by the Licensee and re-turned to the Staff for finalization by the end of February,1981. Draft SER's issued by the NRC subsequent "to January 15, 1981 vill be processed and returned to the Staff within the time interval allotted by the NRC.
CYAPCO and NNECO vill actively assist the Staff in developing the initial evaluations for those topics which the Haddam Neck Plant or Millstone Unit No.1 has been assigned Lead Plant Status, as part of the attempt to com-plete 60% of the SEP topics by June 30, 1981.
In order for these goals to be realized by the Staff and the SEP Owners Group, the Staff's resources are expected to be concentrated toward prompt issuance of draft SER's and 30 day review response on licensee topic assessment sub-mittals. Since the Staff has employed consultants to perform certain evaluations, particularly in the electrical and instrumentation and control areas, it would appear expedient for the consultants to develop draft SER's in advance on each of their topics for each of the plants, rather than have them judge a licensee's topic assessment and then generate an SER.
In response to the conditions specified in Reference (1):
(1) CYAPC0 and NNECO agree to complete the SEP topic assessments specified in Attachments 1 and 2 for the Haddam Neck Plant and Millstone Unit No.1, respectively, for Staff review by June 30, 1981 such that a 60% aggregate total of assessments shall have been submitted for review.
(2) CYAPCO and NNECO commit to actively support the NRC Staff review of the SEP lead topic evaluations in accordance with the 60% goal and June 30, 1981 date.
It should be understood that CYAPCO and NNECO as members of the SEP Owners Group vill attempt to support the Staff's lead topic assessments for each topic by June,1981:
bovever, some of the long-lead or criteria deficient topics may preclude completion of that objective.
(3) CYAPC0 and NNECO, as members of the SEP Owners Group, agree to the 90 day trial period.
(h ) CYAPCO and NNECO see no need to return to the " Lead Plant" concept.
(5) If the Staff is considering expanding this condition to include other licensees, CYAPCO and NNECO vould object strongly.to assign-ing a local representative in Bethesda.
. (6) CYAPCO and NNECO agree that the SEP Owners Group should meet periodically (bi-monthly) with NRC SEP management to discuss SEP progress and program planning.
CYAPCO and NNECO agree "o process draft SER's and advise the (7) t NRC SEP Staff of findings within the 30 day response period.
CYAPC0 and NNECO and the SEP Owners Group appreciate the Staff's adoption of the Owners Group plan to implement resolution of SEP topics preparatory to the development of the integrated assessment position of the program for each of the SEP plants. It is anticipated that the commitments specified above satisfy the Staff requirements to attain topic resolution.
Attachments 1 and 2 for the Haddam Neck Plant and Millstone Unit No.1, respectively, enumerate the SEP Topics which CYAPCO and NNECO intend to complete by June 30, 1981 to satisfy condition (1) above. The topics fall into four categories: generic, deleted, lead plant, and candidates for completion by June, 1981. CYAPCO has negotiated a minor change from the NRC's assignments of Lead Plant Topics. To facilitate timely completion of one specific SEP topic, CYAPC0 has assumed lead plant responsibility for Topic VII-2, ESF System Control Logic and Design from Rochester Gas and Electric. Rochester Gas and Electric has in turn assumed lead plant responsibility for 'Ibpic V-11.B, RER Interlocks. It should be noted that the topics listed in each attachment, in the aggregate, constitute greater than 60% completion by June 30, 1981. Thus, unforseen delays which could preclude completion of certain topic assessments by June 30, 1981 should not prevent CYAPC0 or NNECO from attaining the 60% completion goal.
CYAPC0 and NNECO are concerned that SECY-81-13 as discussed during a com-missioner's briefing on January lb,1981, and made publicly available that same date may preclude the orderly completion of SEP as presently con-stituted. SECY-81-13 could be interprett. ' to state that the present SEP addresses Section 110 of Public Law 96-295 since the topics were obtained from an engineering issue approach which re ~ieved at least 1,100 issues to determine those issued of greatest potents.1 safety significance. The 13T issues culled from the list are those deened to have the greatest potential for safety significance and therefore, address the Section 110 require-ment to review regulations of particular safety significance.
Although the Staff has expressed its intention to efficiently integrate the requirements of Public Law 96-295 into the ongoing IREP and SEP, it is clear that an independent effort to document deviations from a revised Standard Review Plan would not fulfill that intent. There are inadequate resources to support three comprehensive plant assessments simultaneously.
By letter dated November 24,.1980, CYAPC0 and NNECO provided comments 'on Federal Register notice dated October 9,1980 on this subject. Our suggestion to exempt the SEP and IREP plants from any SRP comparison
s-program is reiterated.
If this understanding of SECY-81-13 ts incorrect in any major way and new requirements vill be imposed upon the SEP plants as a result of the
- implementation of SECY-81-13, total. reevaluation of the SEP, its scheduled completion, and the above commitments vill be required.
We trust you will find this information responsive to your request.
l Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMAPNY 84 i
W.'G. Counsil
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Senior Vice President 4
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Docket No. 50-213 o
b ATTACIE4E?ff 1 Haddam Neck Plant SYSTEMATIC EVALUATION PROGRAM REDIRECTION I
February, 1981
i HADDAM NECK PLANT P
Generic Topics Topic No.
Title 11-2.B Onsite Meteorological Measurements Program 11-2.0 Availability of Meteorological Data in the Control Room 111-8.A Loose Parts Monitoring and Core Barrel Vibration Monitoring 111-8.D Core Supports and Fuel Integrity 111-9 Support Integrity 111-11 Component Integrity 111-12 Environmental Qualification of Safety Related Equipment V-1 Compliance with Codes and Standards V-3 Overpressurization Protection V-4 Piping and Safe End Integrity V-7 Reactor Coolant Pump Overspeed V-8 Steam Generator Integrity V-13 Water Hammer Vl-2.B Subcompartment Analysis Vl Combustible Gas Control Vl-6 Containment Leak Testing Vl-7.D Long Tenn Cooling - Passive Failures Vl-7.E ECCS Sump Design and Test for Recirculation Mode Effectiveness Vl-8 Control Room Habitability Vll-1.B Trip Uncertainty and Setpoint Analysis Review.
of Operating _ Data Base 1
HADDAM NECK PLANT - Generic Topics (cont'd.)
Topic No.
Title Vll-4 Effects *of Failure in Non-Safety Related Systems on Selected Engineered Safety Features
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V11-5 Instrumen'ts for Monitoring Radiation and Process Variables During Accidents V11-6 Frequency Decay V111-1.A Potential Equipment Failures Associated with Degraded Grid Voltage 1X-2 Overhead Handling Systems - Cranes 1X-6 Fire Protection X1-1 Appendix I X1-2 Radiological (Effluent and Process) Mcnitoring Systems X111-1 Conduct of Operations X111-2 Safeguards / Industrial Security XV-21 Spent Fuel Cask Drop Accidents XV-22 Anticipated Transients Without SCRAM XV-23 Multiple Tube Failures in Steam Generators XV-24 Loss of All A-C Power XV11 Operational QA Program s h%
HADDAM NECK PLANT Deleted Topics Topic No.
Title 11-4.E Dam Integrity 111-7.A Inservice Inspection, Including Prestressed Concrete Containments with Either Grouted or Ungrouted Tendons ill-7.C Delamination of Prestressed Concrete Containment Structures ill-8.B Control Rod Drive Mechanism Integrity 111-10.C Surveillance Requirements on BWR Recirculation Pumps and Discharge Valves lV-3 BWR Jet Pump Operating Indications V-2 Applicable Code Cases V-9 Reactor Core Isolation Cooling System V-12 Water Purity of BWR Primary Coolant Vl-2.A Pressure-Suppression Type BWR Containments Vl-2.C Ice Condenser Containment Vl-7.A.2 Upper Plenum Injection l
Vl-7.A.4 Core Spray Nozzl2 Effectiveness Vl-7.F Accumulator Isolation Valves Power and Control
System Design
l Vl-9 Main Steam Line Isolation Seal. System V1-10.B Shared Engineered Safety Features, On-Site Emergency Power, and Service Systems for Multiple Unit Facilities Vll-7 Acceptability of Swing Bus Design on BWR-4 Plants XV-11 Inadvertent Loading and Operation of a Fuel-Assembly-in an Improper Position XV-13 Spectrum of Rod Drop' Accidents.
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4 Topic No.
Title XV-18 Radiological Consequences of Main Steam Line Failure Outside Containment XVI Technical Specifications
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P Lead Plant Topics I
e Topic No.
Title j.
il 11-2.C Atmospheric Transport and Diffusion Characteristics for Accident Analysis 111-2 Wind and Tornado Loadings 111-3.B Failure of Underdrain Systems i
i lil-4.A Tornado Missiles ill-10.A Thermal-0verload Protection for Motors of Motor-0perated Valves V-5 Reactor Coolant Pressure Boundary Leakage Detection j
Vl-10.A Response Time Testing RTS.and ESF i
V11-2 ESF System Control Logic and Design Vill-2 Onsite Emergency Power Systems-Diesel i
Generator.
Vill-3.B DC Power System Bus Voltage Monitoring and Annunication 1X-4 Boron Addition System I
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HADDAM NECK PLANT Candidates for Completion by June, 1981 Topic No.
Title 11-1.A Exclusion Area Authority and Control l
ll-1.B Population Distribution i
ll-1.C Potential Hazards or Changes in Potential Hazards l
Due to Transportation, Institutional, Industrial, and Military Facilities ll-2.A Severe Weather Phenomena lil-7.D Containment Structural Integrity Tests lil-8.C Irradiation Damage, Use of Sensitized Stainless Steel and Fatigue Resistance 111-10.B Reactor Coolant Pump Flywheel Integrity IV-1.A Operation With Less Than All Loops in Service V-10.A RHR Heat Exchanger Tube Failures-j l
V-ll.A High and Low Pressure System Isolation V-ll.B RHR Interlock Requirements Vl-4 Containment Isolation System Vl-7.C.1 Independence of Redundant Onsite Power Systems l
Vll-3 Safe Shutdown V111-3.A Station Battery Test Requirements Vill-4 Electrical Penetrations of Reactor Containment XV-19 Loss of Coolant Accidents Resulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant Pressure Boundary i
h Docket No. 50-245
(
ATTACINDIT 2 Millstone Nuclear Power Station, Unit No.1 SYSTEMATIC EVALUATION PROGRAM REDIRECTION February, 1981
Millstone Unit No. 1 n
Generic Topics Topic No.
Ti tl_e_
ll-2.B Onsite Meteorological Measurements Program 11-2.D Availability of Meteorological Data in the Control Room 111-8.A Loose Parts Monitoring and Core Barrel Vibration Monitoring lil-8.B Control Rod Drive Mechanism Integrity ill-8.D Core Supports and Fuel Integrity 111-9 Suppoc t Integrity 111-11 Component Integrity 111-12 Environmental Oualificetion of Safety Related Equipment 1V-3 BWR Jet Pump Operating Indications V-1 Compliance with Codes and Standards V-4 Piping and Safe End Integrity V-13 Water Hammer Vl-2.A Pressure-Suppression Type BWR Containments Vl-2.B Subcompartment Analysis Vl-5 Combustible Gas Control Vl-6 Containment Leak Testing Vl-7.A.4 Core Spray Nozzle Effectiveness Vl-7.D Long Term. Cooling - Passive Failures V1-8 Control Room Habitability i
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Millstone Unit No. 1 - Generic Topics (cont'd.)
Topic No.
Title Vil-1.B Trip Uncertainty and Setpoint Analysis Review of Operating Data Base l.
V11-4 Effects of Failure in Non-Safety Related Systems on l-Selected Engineered Safety Features Vll-5 Instruments for Monitoring Radiation and Process Variablec During Accidents Vll-6 Frequency Decay V111-1.A Potential Equipment Failures Associated with Degraded Grid Voltage 1X-2 Overhead Handling Systems - Cranes IX-6 Fire Protection X1-1 Appendix I X1-2 Radiological (Effluent and Process) Monitoring Systems Xill-1 Conduct of Operations X111-2 Safeguards / Industrial Security XV-21 Spent Fuel Cask Drop Accidents XV-22 Anticipated Transients Without SCRAM XV-24 Loss of All A-C Power XVil Operational QA Program l
Millutone Unit No. 1 Deleted Topics Topic No.
Title 11-4.E Dam Integ'rity 111-3.B Structural and Other Consequences of Failure of Underdrain Systems 111-7.A Inservice Inspection, Including Prestressed Concrete Containments with Either Grouted or Ungrouted Tendons 111-7.C Delamination of Prestressed Concrete Containment Structures 111-10.B Pump Flywheel Integrity V-2 Applicable Code Cases V-3 Overpressurization Protection V-7 Reactor Coolant Pump Overspeed V-8 Steam Generator Integrity V-9 Reactor Core Isolation Cooling System V1-2.C Ice Condenser Containment V1-7.A.1 ECCS Reevaluation to Account for Increased Vessel Head Temperature V1-7.A.2 Upper. Plenum Injection V1-7.B
- ESF Switchover from Injection to Recirculation Mode V1-7.C.3 Effect of PWR Loop Isolation Valve Closure During a LOCA on ECCS Performance-V1-7.E ECCS Sump Design and Test for Recirculation Mode Effectiveness V1-7.F Accumulator 1 Isolation Valves Power.and Control-
. System Design V1-9
' Main Steam Line Isolation Seal System:
V11 Acceptability of Swing Bus Design on BWR-4 Plants
Millstone Unit No. 1 - Deleted Topics (cont'd.)
Topic No.
Title 1X-4 Boron Addition System X
Auxiliary Feedwater System l
XV-2 Spectrum of Steam System Piping Failures Inside and Outside of Containment XV-6 Feedwater System Pipe Breaks Inside and Outside Containment XV-10 Chemical and Volume Control System Malfunction That Results in a Decrease in the Boron Concentration in the Reactor Coolant XV-12 Spectrum of Rod Ejection Accidents XV-17 Radiological Consequences of Steam Generator Tube Failure XV-23 Multiple Tube Failures in Steam Generators i
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Millstone Unit No.1 Lead Plant Topics l
Topic No.
Title 111-4.C Internally Generated Missiles i
I 111-4.D Site Proximity Missiles V-12.A Water Purity of Boiling Water Reactor Primary Coolant i
V1-10.B Shared Systems i
V111-4 Electrical Penetration of Reactor Containment XV-13 Spectrum of Rod Drop Accidents XV-18 Radiological Consequences of Main Steam Line Failure Outside Containment l
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Millstone Unit No. 1 Candidates for Completion by June,1981 1
Topic No.
Title b
11-1.A Exclusion Area Authority and Control 11-1.B Population Distribution 11-1.C Potential Hazards or Changes in Potential Hazards Due to Transportation, Institutional, Industrial, and Military Facilities 11-2.A Severe Weather Phenomena 11-2.C Atmospheric Transport and Diffusion Characteristics for Accident Analysis 11-3.A Hydrologic Description 11-3.B Flooding Potential and Protection Requirements 11-3.B.1 Capability of Operating Plant to Cope With Design-Basis Flooding Conditions 11-3.C Safety Related Water Supply (Ultimate Heat Sink) 111-7.D Containment Structural Integrity Test 111-8.C Irradiation Damage, Use of Sensitized Stainless Steel and Fatioue Resistance 111-10.C Surveillance Requirements on BWR Recirculation Pumps and Discharge Valves 1V-1.A Operation With Less Than All Loops in Service V-5 Reactor Coolant Pressure Boundary Leakage Detection j
V-10.A RHR Heat Exchanger Tube F&' lures V1-7.A.3 ECCS Actuation System-V11-3 Systems Required for Safe Shutdown V111-2 Onsite Emergency Power Systems - Diesal Generator
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Millstone Unit No.1 - Candidates for Completion by June,1981 (cont'd.)
P Topic No.
Title Vill-3.A-Station Battery Capacity Test Requirements XV-19 Loss of Coolant Accidents Resulting from Spectrum of Postulated Pipe Breaks Within the Reactor Coolant Pressure Boundary 4
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