ML20003J254

Clarifies Requirements of Generic Ltrs Issued Subsequent to Accident & Informs of Plans for Processing Future Generic Ltrs.List of Generic Ltrs Issued Since TMI-2 Accident Encl

ML20003J254
Person / Time
Site:	Crane
Issue date:	05/04/1981
From:	Snyder B Office of Nuclear Reactor Regulation
To:	Hovey G METROPOLITAN EDISON CO.
References
NUDOCS 8105110117
Download: ML20003J254 (14)

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Distribution:

VDocket No. 50-320 I&E(3)

MAY 4 L

NRC PDR ACRS (16)

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LPDR RBellamy Docket No. 50-320

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9 TMIP0 R/F Service List A % TMI Site R/F (see attached) g j

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-- Mr. Gale K. Hovey

'1l AFasano (TMI Site) 1 Vice President and ei RConte (TMI Site)

Director of TMI-2 p

MDuncan Metropolitan Edison Company g /'Nj LChandler, ELD P.O. Box 480 Middletown, Pennsylvania 17057 DBrinkman 0 Lynch

Dear Mr. Hovey:

RWeller Recent discussions between stars of our staffs have indicated that an uncertainty exists regarding your required responses to generic letters which have been issued subsequent to the TMI-2 accident. This letter is intended to clarify the requirements of these generic letters as they apply to TMI-2 and to infom you of our plans for processing future generic letters applicable to TMI-2.

We have reviewed the list of generic letters which have been issued subsequent to the TMI-2 accident and we agree that due to the present condition of TMI-2, some of these letters are not presently applicable, however, we believe that certain of these generic letters are applicable and tnat you should review their requirements and take appropriate actions. Attached for your infomation is a listing of generic letters issued since the THI-2 accident. We have re-viewed this listing and have indicated those entries which apparently are not applicable to TMI-2. You are requested to also review this listing and for those subjects which require a response and are determined applicable to THI-2, provide the requested response (s) no later than 90 days from the date of this letter. If at some future time, you decide to mfurbish and recosuiission TMI-2, we will then of course require that you appropriately address each of the listed generic issues. Until such a decision is made, we will screen out-going generic letters to determine their applicability to TMI-2. Those deter-mined currently applicable to THI-2 will be sent to you by this office rather than by the Division of Licensing.

If you desire further discussions on these generic issues you may contact Donald Brinkman of my staff at (301) 492-4857.

Sincerely,

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Bernard J. Snyder, Program Director TMI Program Office M05 J J o //7, Office of Nuclear Reactor Regulation __

Enclosure:

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s LIST OF GENERIC LETTERS ISSUED SINCE TMI-2 ACCIDENT DATE SUBJECT 5/15/79*

Westinghouse two loop NSSS 5/15/79*

All PWRs Cracking in Feedwater Lines 5/21/79*

NRC Staff Review of Responses to I&E Bulletin 79-06 and 79-06A 6/4/79 All Power Reactor Licensees Enclosing NUREG/CR 0660 " Enhancement of Onsite Emergency Diesel Generator Reliability" 6/11/79*

All Power Reactor Licensees Enclosing NUREG-0560 " Staff Report on the Generic Assessment of Feedwater Transients in Pressurized Water Reactors Designed by the B&W Company" 6/11/79*

Infonnation Copy of Request for Additional Information Regarding Westinghouse Small Break LOCA Analysis 6/20/79*

All BWRs NRC Staff Review of Responses to I&E Bulletin 79-08 6/26/79*

All Pressurized Water Reactors Multiple equipment failures in safety-related systems 6/29/79 All Power Reactor Licensees Information Required to Review Corporate Capabilities 7/13/79*

Additional Information Required for NRC Staff Generic Report on BWRs 1

7/16/79*

All BWRs except Big Rock and Humboldt Bay Operability Testing of Relief and Safety Relief Valves 7/18/79*

Al1 BWRs Transmitting NUREG-0473, Revision 2,' Draft Radiological Effluent Technical Specifications" 7/18/79*

All PWRs Transmitting NUREG-0472, Revision 2," Draft Radiological l

Effluent Technical Specifications" 7/25/79*

All Power Reactor Licensees Transmitting NUREG-0578 "TMI-2 Lessons Learned..."

7/30/79 All Power Reactor Licensees Transmitting NUREG-0576 " Security Training and Qualifications Plans" 8/3/79 All Power Reactor Licensees Regional meetings to discuss impacts on emergency planning

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. DATE SUBJECT 8/8/79 All Power Reactor Licensees (Except Humboldt Bay)

Adequacy of Station Electric Distribution System Voltages 8/10/79 All Power Reactor Licensees Amendment to 10 CFR 73.55 deferral from 8/1/79 to 11/1/79 8/22/79*

All BWRs (Except Humboldt)

BWR off-gas systems enclosing NUREG/CR-0727 9/13/79*

All Operating Nuclear Power Plants Followup Actions Resulting from the NRC Staff Reviews Regarding the TMI-2 Accident 9/17/79 All Power Reactor Licensees Compliance with 40 CFR 190, EPA Uranium Fuel Cycle Standard 9/17/79*

All Operating Light Water Reactors Potential Unreviewed Question on Interaction Between Non-Safety Grade Systems and Safety Grade Systems 9/18/79*

Reactor Cavity Seal Ring Generic Issue (PWR) 9/21/79*

All Pressurized Water Reactors Referencing 6/26/79 letter re multiple equipment failures 9/25/79 All Power Reactor Licensees Transmittal of Reports Regarding Foreign Reactor Operating Experiences 9/27/79*

All Light Water Reactors Containment Purging and Venting During Normal Operations -

Guidelines for Valve Operability 10/2/79 All Power Reactor Licensees Radiation Training 10/2/79*

All BWRs (Except Dresden 1, Humboldt Bay, Big Rock, Lacrosse)

Confirmatory Requirements Relating to Condensation Oscillation Loads for the Mark I Containment Long Term Program 10/5/79*

All Power Reactor Licensees Sumary of Meetings Held on 9/18-20/79 to Discuss a Potential Unreviewed Safety Question on Interaction Between non-safety Grade Systems and NSSS Supplied Safety Grade Systems (I&E Information Notice 79-22) 10/10/79 All Power Reactor Licensees Emergency Plans submittal dates 10/17/79 All Operating Nucler Power Plants Radioactive Release at North Anna Unit 1 and Lessons Learned

O

. DATE SUBJECT 10/17/79*

All Power Reactor Licensees All Applicants with Applications for a License ATWS 10/22/79*

Containment Purge and Venting During Normal Operation 10/13/79*

All Pressurized Water Reactor Licensees Summary of Meeting Held on October 12, 1979, to Discuss Responses to IE Bulletins79-05C and High Pressure Injection (HPI) Termination Criteria 10/30/79*

All Operating Nuclear Power Plants Discussion of Lessons Learned Short Term Requiremar..s 10/31/79*

Acceptable Criteria for the Mark I Containment Long Term Program 11/9/79*

All Operating Light Water Reactors ECCS calculations on fuel cladding 11/27/79 All Power Reactor Licensees Radiological Environmental Monitoring Program Requirements enclosing Branch Technical Position, Revision 1 11/27//9*

011 Operating Light Water Reactors Additional Information re 11/9/79 letter 11/29/79 All Power Reactor Licensees Estimates for Evacuation of various areas Around NucIcar Power Reactors 12/17/79*

All Operating Nuclear Power Plants Audit of Small Break LOCA Guidelines 12/20/79*

All Power Reactor Licensees Cladding Rupture, Swelling and Coolant Blockage As a Result of a Reactor Accident l

12/21/79 All Power Reactor Licensees t

All Construction Permit Holders and Applicants Proposed Rule on Radiological Emergency Response Plans 1/3/80*

All Power Reactor Licensees NUREG-0630 " Cladding, Swelling and Rupture - Mcdels for LOCA Analysis" 1/7/80 All Power Reactor Licensees (Except Arkansas Nuclear One, Units 1 and 2)

Quality Assurance Requirements Regarding Diesel Generator i

Fuel Oil

. DATE SUBJECT 1/10/80*

All BWR Licensees (Except Humboldt Bay)

BWR Control Rod Failures 1/11/80*

All BWR Power Reactor facilities with an OL IEB 80-01 Operability of ADS Valve Pneumatic Supply 1/14/80*

All Power Reactor Facilities with an OL IEB-79 01B Environmental Qualification of Class IE Equipment 1/21/80*

All BWR Licensees with a CP or OL IEB 80-02 Inadequate Quality Assurance for Nuclear Supplied Equipment 1/29/80 All Power Reactor Licensees Low Level Radioactive Waste Disposal 2/6/80*

All Holders of Power Reactor OLs and cps IEB 80-03 Loss of Charcoal from Standard Type II, 2 Inch, Tray Adsorber Cells 2/8/80*

All PWR Reactor Facilities Holding OLs and to those nearing Licensing IEB 80-04 Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition 2/23/80*

All LWR Licensees LWR Primary Coolant System Pressure Isolation Valves 2/29/80*

All Power Reactor Facilities with an OL IEB 79-01B Environmental Qualification of Class IE Equipment 3/6/80*

All Operating B&W Reactor Licensees Crystal River 3 Reactor Trip from Approximately 100% Full Power 3/10/80*

All LWRs Enhanced Fission Gas Release 3/10/80 All PWR Power Reactor Facilities holding OLs and to those with a CP IEB 80-05 Vacoum Condition Resulting in Damage to Chemical Volume Control System (CVCS) Holdup Tanks 3/10/80 All Power Reactor Licensees and Applicants for a License to Operate a Nuclesr Power Reactor (FSAR Docketed)

Emergency Planning. Transmitting NUREG-0654

" Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants (For Interim Use and Comment)."

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DATE SUBJECT 3/12/80*

All Operating Nuclear Plants NRC Nuclear Data Link (NDL) 3/13/80*

All Power Reactor Facilities with an OL IEB 80-86 Engineered Safety Feature (ESF)

Reset Controls 3/28/80 All Pcwer Reactor Applicants and Licensees Qualifications of Reactor Operators 4/4/80*

All GE BWR-3 and BWR-4 Facilities with an OL IEB 80-07 BWR Jet Pump Assembly Failure 4/7/80*

All Power Reactors with a CP and/or OL no later than April 7,1980 IEB 80-08 Examination of Containment Liner Penetration Welds 4/7/80*

All BWR Licensees Modification to Boiling Water Reactor Control Rod Drive Systems' 4/10/80 All Power Reactor Licensees Operability of Systems 4/17/80*

All Power Reactor Operating Facilities and Holders of Power Reactor Construction Pennits IEB-80-09 Hydramotor Actuator Deficiencies i

4/25/80*

All Power Reactor Licensees Clarification of NRC Requirements for Emergency Response Facilities at Each Site 4/25/80*

Individual Licensees Effect of a DC Power Supply Failure on ECCS Performance 5/6/80*

All Power Reactor Facilities with an OL or CP IEB 80-10 Contamination of Non-radioactive System and Resulting Potential for Unmonitored, Uncontrolled Release to Environment 5/7/80 All Operating Reactor Licensees Five Additional TMI-2 Related Requirements to Operating Reactors 5/8/80 All Power Reactor Facilities with an OL, except Trojan IEB 80-11 Masonry Wall Design

s I

6-DATE SUBJECT 5/8/80*

Individual Licensees Transmitting NUREG-0645 " Report of the Bulletins and Orders Task Force"and appropriate NUREG-0626 " Generic Evaluation of Feedwater Transients and Small Break Loss-of-Coolant Accidents" 5/9/80*

Each PWR with an OL IEB 80-12 Decay Heat Removal System Operability 5/12/83*

All BWR's with an OL IEB 80-13 Cracking in Core Spray Spargers 5/19/80 All Licensees with Reactor Operating Licenses Issued Prior to January 1,1979 Fire Protection Rule. Enclosing proposed rule

" Fire Protection Program for Nuclear Power Plants Operating Prior to Jan.1,1979 5/19/80*

All Power Reactor Licensees Generic Technical Activity A-12 i

Fracture Toughness 5/22/80 All Licensees with Reactor Operating Licenses Issued Prior to January 1,1979 Fire Protection Rule. Enclosing revised pages to 5/19/80 letter on Fire Protection.

6/3/80*

Individual Licensees Nuclear Safeguards Problems 6/5/S0*

All BWR Licensees Generic Activity A EWR Cracks 6/9/80 All Operating Reactor Licensees Five Additional TMI-2 Related Requirements.

Transmitting errata sheets to May 7 letter on five additional TMI-2 related requirements.

6/11/80*

All Operating Pressurized Water Reactors Decay Heat Removal Capability 6/12/80*

All BWR's with an OL IEB 80-14 Degracation of Scram Discharge Volume Capability e

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. DATE SUBJECT 6/18/80 All Nuclear Facilities Holding OLs IEB 80-15 Possible Loss of Hotline with Loss of Off-Site Power. Report that all ENS facilities would remain operational with a loss of offsite power 6/25/80 All Power Reactor Applicants and Licensees Comission Memorandum and Order (EQ).

Transmitting Memorandum and Order dated May 27,1980, re fire protection for electrical cables, and environmental qualification of electrical components 6/27/80*

All Power Reactor Facilities with an OL or a CP IEB 80-16 Potential Misapplication of Rosemount Inc., Models 1151 and 1152 Pressure Transmitters with Either "A" e "0" Output Codes, 6/30/80*

All Applicants ror Construction Permits, Power Reactor Licensees Architect / Engineers and Reactor Vendors Meetings on EQ. Transmitting Federal Register Notice re Regional Meetings to discuss environ-mental qualifict tion of electrical equipment 7/2/80*

All Pressurized Water Reactor Licensees TMI-2 Lessons Learned. Enclosing Model Technical Specifications for NUREG-0578 TMI-2 Lessons Learned Category A Items, requires submittal l

I 7/2/80*

All Boiling Water Reactor Licensees TMI-2 Lessons Learned. Enclosing Model Technical Specifications for NUREG-0578 TMI-2 Lessons Learned Category A Items, requires submittal 7/3/80*

All BWR Power Reactor Facilities Holding OLs IEB 80-17 Failure of Control Rods to Insert During a Scram at a BWR 7/7/80*

All Boiling Water Reactors Scram Discharge Volume Designs 7/11/80*

To All Applicants for Operating Licenses and Construction Permit Holders Licensing Schedule 7/18/80*

All BWR Power Reactor Facilities Holding OLs IEB 80-17 Supplement 1 Failure of Control Rods to Insert During a Scram at a BWR

4 DATE SUBJECT 7/22/80*

All Boiling Water Reactors Scram Discharge Volume 7/22/80*

All BWR Power Reactors IEB 80-17 Supplement 2 Failures Revealed by Testing Subsequent to Failure of Control

~ Rods to Insert During a Scram at a BWR 7/24/80*

All PWR Power Reactor Facilities Holding OLs and to those PWRs nearing Licensing IEB 80-18 Maintenance of Adequate Minimum Flow Thru Centrifugal Charging Pumps Following Secondary Side High Energy Line Rupture 7/31/80*

All Nuclear Power Facilities Having Either an OL or a CP IEB 80-19 Failures of Mercury-Wetted Matrix Relays in Reactor Protective Systems of Operating Nuclear Power Plants Designed by Combustion Engineering 7/31/80 To Each Nuclear Power Facility in your Region having an OL or a CP IEB 80-20 Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches 7/31/80 All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permi ts Interim Criteria for Shift Staffing. Requires I

the development and implementation of adminis-trative procedures by 10/31/80 8/1/80 All Applicants for Construction Permits, Licensees of Plants Under Construction and All Operating i

Nuclear Power Plants l

" Functional Criteria for Emergency Respoase Facilities" l

NUREG-0696 8/7/80*

All Operating Power Reactor Licensees Lessons Learned Tech Specs. Referencing Letters of

(

7/2/80 and requesting Amendment Fee Classification 8/15/80*

All Westinghouse Pressurized Water Reactor Licensees Refueling Water Level

, - -. -,,..,,,.. ~ -.

-g-DATE SUBJECT 8/20/80*

All BWRs with Mark I Containment Mark I Containment Long-Term Program i

8/22/80*

All BWR Power Reactor Facilities Holding OLs IEB 80-17 Supplement 3 Failures Revealed by Testing Subsequent to Failure of Control Rods to Insert During a Scram at a BWR 9/5/80*

All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits Preliminary Clarification of TMI Action Plan Requirements 9/19/80*

All Licensees of Operating Reactor Plants and Applicants for Operating Licenses and Holders of Construction Pennits Preliminary Clarification of TMI Action Plan Requirements. Addendum to 9/5 letter.

9/30/80*

All Power Reactor Facilities with an OL IEB 79-01B Supplement 2 Environmental Qualification of Class IE Equipment 10/1/80*

All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permi ts Environmental Qualification of Safety-Related Equipment 10/1/80*

All BWR Licensees BWR Scram System 10/6/80*

All Power Reactor Licensees and Applicants Implementation of Guidance from Unresolved l

Safety Issue A-12 " Potential for Low Fracture Toughness and Lamellar Tearing on Component Supports" 10/21/80*

All Operating Pressurized Water Reactor Licensees Seismic Qualification of Auxiliary Feedwater Systems 10/24/80*

All Power Reactor Facilities with an OL IEB 79-01B Supplement 3 Environmental Qualification of IE Equipment l

10/31/80*

All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits Post TMI Requirements NUREG-0737

e DATE SUBJECT 11/4/80*

All Hclders of Construction Permits and Operating Licenses for BWRs ODYN Code Calculation 11/6/80 All Light Water Reactor Facilities Holding OLs or cps IEB 80-21 Valve yokes supplied by Malcolm Foundry Company, Inc.

Report on inspection and corrective actions concerning Malcolm valve yokes 11/13/80 All Licensees of Operating Reactor Plants, Holders of Construction Pennits and Applicants for Construction Permits Emergency Plan. Describes submittal schedules of new rule 11/13/80*

All BWR Licensees Generic Activity A-10 11/14/80 All Power Reactors Fire i ntection. Forwards new Section 50.48 and Appendix R, Discusses schedules and SERs 11/14/80 All Nuclear Power OL or CP IEB 80-23 Failures of Solenoid Valves Engineering Corporation. Report on use and replacement schedule for affected valves 11/20/80*

All Power Reactors with OLs IEB 80-24 Prevention of Damage due to Water Leakage Inside Containment 11/24/80 All Power Licenses with Plants Licensed prior to January 1,1979 Appendix R to 10 CFR 50 re. Fire Protection.

Fomards new regulations, lists open items concerning fire protection for each facility 11/25/80 Operating Reactors with Prestressed Concrete Containment Structures Inservice Inspection Programs. Requests voluntary infomation on containment tendon tests l

11/25/80 To All Power Reactor Licensees with Plants Licensed Prior to January 1,1979 Fire Protection. Forwards revised Federal Register Notice l

4 DATE SUBJECT 11/26/80*

All Licensees of Operating Plants and Applicants for Operating Licenses and Holders of Construction Permits Orders on Environmental Qualification of Safety Related Electrical Equipment. Pro-vides clarification on record requirements 12/9/80*

To All BWR Licensees BWR Scram Discharge System 12/9/80 All Licensees of Operating Reactor Plants, Holders of Construction Permits and Applicants for Construction Permits Emergency Planning. Forwards 1) NUREG-0654, Revision 1 " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" and 2) sumary rating sheets for evacuation time estimates.

All Operating Reactor Licensees 12/15/80 Periodic Updating of FSARs.

Forwards new rule and guidance in the form of questions and answers 12/18/80*

All BWR Licensees IEB 80-17 Supplement 4 Failure of Control Rods to Insert Du:/ing a Scram at a BWR 12/19/80*

All BWR Power Reactor Facilities with an OL and Fermi 2, Shorehan IEB 80-25 Operating Problems with Target Rock Safety Relief Valves 12/22/80*

All Licensees of Operating Plants and Applicants for Operating Licenses and Permits Control of Heavy Loads.

(Sent to TMI-2 on 2/27/81, letter to Hovey from Snyder.)

1/19/81*

Information Regarding the Program for Environmental Qualification of Safsty-Related Electrical Equipment 1/23/81*

BWR Scram Discharge System 1/27/81 Analysis, Conclusions, and Recommendations concerning Operator Licensing 1/29/81*

ODYN Code 2/3/81*

Control of Heavy Loads.

(Sent to TMI-2 on 2/27/81, letter to Hovey from Snyder.)

---~-r

. DATE SUBJECT _

2/10/81*

Seismic Qualifications for Auxiliary Feedwater Systems 2/18/81 Post-TMI Requirements for the Emergency Operation

• Facility BWR Feedwater Nozzle and Control Rod Drive 2/20/81*

Return Line Nozzle Cracking (NUREG-0619)

Fire Protection Rule (45 FR 76602,11/19/80) 2/20/81 2/25/81 Emergency Procedures & Training for Station Blackout Events Periodic Updating of Final Safety Analysis 2/26/81 Reports (FSARs) 2/26/81*

Implementation of NUREG-0313 " Tech Report on Material Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping" 3/5/81 Emergency Resp. Facility (NUREG-0696) 3/10/81*

Envir. Qualif. of Class IE Electrical Equip.

l 3/30/81*

BWR Scram Discharge System; Clarification of Diverse Instrumentation Requirement

• Does not appear applicable to TMI-2 at this time, i

l l

I

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