ML17056B322
| ML17056B322 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/15/1991 |
| From: | Brinkman D Office of Nuclear Reactor Regulation |
| To: | Sylvia B NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 9102210038 | |
| Download: ML17056B322 (60) | |
Text
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,1 cv Docket No.
50-220 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Sylvia:
Distribution:
'DI-1-Readin'g EGreenman DBrinkman JLinville EJordan Plant File
~ ruary 15, 1991 NCR 5 Local PDRs SVarga CVogan RACapra OGC ACRS (10)
SUBJECT:
IMPLEMENTATION OF NRC BULLETINS AND GENERIC LETTERS AT NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 The NRC staff has recently been reviewing the implementation status of NRC bulletins and generic letters issued since the Three Mile Island Unit No.
2 accident in March 1979.
This review has been coordinated with members of'our staff.
The enclosed tables provide the results of this review as applicable to Nine Mile Point Unit No. 1. Although we believe the enclosed tables accurately reflect the implementation status of these bulletins and generic letters, we request that you review the enclosed tables and confirm their accuracy, or provide any corrections, by February 25, 1991.
Please contact me on (301) 492-1402 if you have any questions regarding this matter.
This requirement affects one respondent, and, therefore, is not subject to Office of Management and Budget review under P. L.96-511.
Sincerely, ORIGINAI.,SIGNED BY~
r Donald S. Brinkman, Senior Project Manager Pr oject Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Key to Table Notations 2.
Table 1 -
NRC Bulletins 3.
Table 2 -
NRC Generic Letters cc w/enclosures:
See next page 9102210038 910215 I
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Docket No. 50-220 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20555 February 15, 1991 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212
Dear Mr. Sylvia:
SUBJECT IMPLEMENTATION OF NRC BULLETINS AND GENERIC LETTERS AT NINE MILE POINT NUCLEAR STATION, UNIT NO.
1 The NRC staff has recently been reviewing the implementation status of NRC bulletins and generic letters issued since the Three Mile Island Unit No.
2 accident in March 1979.
This review has been coordinated with members of your staff.
The enclosed tables provide the results of this review as applicable to Nine Mile Point Unit No. 1.
Although we believe the enclosed tables accurately reflect the implementation status of these bulletins and generic letters, we request that you review the enclosed tables and confirm their accuracy, or provide any corrections, by February 25, 1991.
Please contact me on (301) 492-1402 if you have any questions regarding this matter.
This requirement affects one respondent, and, therefore, is not subject to Office of Management and Budget review under P. L.96-511.
Sincer ely, Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosures:
1.
Key to Table Notations
- 2. Table 1 -
NRC Bulletins
- 3. Table 2 -
NRC Generic Letters cc w/enclosures:
See next page
Hr. B. Ralph Sy 1 via Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit No.
1 CC:
Hr. Hark J. Wetterhahn, Esquire
- Bishop, Cook, Purcell 5 Reynolds 1400 L. Street, N.W.
Washington, D. C.
20005-3502 Supervisor Town of Scriba R.
D.
P4
- Oswego, New York 13126 Nr. Joseph F. Firlit Vice President - Nuclear Generation Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 126
- Lycoming, Nevi Yor k 13093 Hr. Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
- Syracuse, New York 13202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Hs.
Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor
- Albany, New York 12223 Hr. Kim Dahlberg Unit 1 Station Superintendent Nine Nile Point Nuclear Station Post Office Box 32
- Lycoming, New York 13093 Hr. Peter E. Francisco, Licensing Niagara Mohawk Power Corporation 301 Plainfield Road
- Syracuse, New York 13212 Charlie Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Hr. Paul D. Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza
- Albany, New York 12223
Enclosure 1
Ke To Table Notations On Tables 1 and 2
Tables 1 and 2 do not include NRC Bulletins and Generic Letters which were obviously not applicable to NMP-1 (e.g., Bulletins and Generic Letters addressed to only PWRs, etc.).
The column entitled, "Applicable to NMP-1" indicates whether or not upon evaluation, the bulletin or generic letter was determined applicable to NMP-1.
The column entitled, "Response Required" indicates whether or not NMPC was required by the bulletin or generic letter to submit a written response to the NRC; although in some cases a response was not required, NMPC did submit a response and in these cases a response date is indicated.
The column entitled, "Response Date" provides the date a written response was submitted to the NRC if a response was required.
The column
- entitled, "Implementation Date" provides the date PHPC fu I'y implemented the requirements of the bulletin or generic letter.
Page No.
02/13/91 TABLE 1 HRC BULLETINS ENCLOSURE 2 BL->>
TITLE APPLICABLE RESPONSE
RESPONSE
IMPLEMEHTATION TO HMP1 REQUIRED DATE DATE COMHRNTA
+4 YEAR 79 79 79 79 08 Events Relevant to Boiling Water Reactors YES Identified During Three Mile Island Incident-79 79 79 79 79 79 09 10 11 12 13 14 Failures of GE Type AK-2 Circuit Breaker in NO Safety Related Systems Bequalification Training Program Statistics YES Faulty Overcurrent Trip Device in Circuit NO Breakers for Engineered Safety Systems Short Period Scrams at BWR Facilities YES Cracking in Feedwater System Piping NO Seismic Analyses for As-Built Safety-Related YES Piping Systems 79 79 79 79 79 79 15 18 19 21 23 24 Deep Draft Pump Deficiencies Audibi.lity Problems Encountered on Evacuation of Personnel from High-Noise Areas Packaging of Low-Level Radioactive Waste for YES Transport and Burial Temperature Effects on Level Measurements Potential Failure of Emergency Diesel Generator Field Exciter Transformer Frozen Lines YES YES NO YES YES 79 79 79 79 25 26 27 28 Failures of Westinghouse BFD Relays in Safety-Related Systems Boron Loss from BWR Control Blades Loss of Non-Class-1-E Instrumentation and Control Power System Bus During Operation Possible Malfunction of HAMCO Model EA180 limit Switches at Elevated Temperatures NO YES YES HO 79 06 Review of Operational Errors and System NO Misalignments Identified During the Three Mile Island Incident 08A Review of Operational Errors and System NO Misalignments Identified During the Three Mile Island Incident 06B Review of Operational Errors and System HO Misalignments Identified During the Three Mile Island Incident 06C Review of Operational Errors and System NO Misalignments Identified During the Three Mile Island Incident 07 Seismic Stress Analysis of Safety-Belated YES Piping NO HO NO NO YES YES NO YES NO YES NO YES YES YES YES HO YES YES YES YES NO
/ /
/ /
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/ /
/ /
/ /
/=/
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06/12/79 06/19/79 05/14/79 05/21/80 05/07/79
/ /
05/21/79 05/21/79 07/30/79 05/21/79 07/30/79 05/27/81
/ /
/ /
08/17/79 04/25/89 12/05/89 12/12/89 09/19/79 09/19/79 01/04/80 04/17/81
/ /
/ /
10/26/79 12/31/79 10/24/79
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11/26/79
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12/17/79 12/17/79 02/29/80 02/29/80 01/04/80
/ /
06/19/79 CLOSED BY NRC MORE THAN ONE
RESPONSE
ClOSED BY NRC 5/21/80 SE MORE THAN ONE RESPOHSE DATE LICENSEE SUBMITTED
RESPONSE
ADDITIONALWALKDOWHS TO BE PERFORMED DURING ENGINEERING PROGRAM IHTEGRATION NRC CLOSED 10/18/90 NO FORMAL HRC
RESPONSE
BACK NO FORMAl NRC
RESPONSE
BACK HO IMPLEMENTATION DATE REQUIRED LICENSEE SUBMITTED
RESPONSE
LICENSEE SUBMITTED
RESPONSE
Page No.
02/13/91 BL-o TITLE TABLE 1 HRC BULLETIHS APPLICABLE RESPONSE RESPOHSE IMPI EMEHTATION TO HMP1 REQUIRED DATE DATE COMMEHTS
+4 YEAR 80 80 01 80 02 80 03 80 06 Inadequate Quality Assurance for Nuclear Supplied Equipment Loss of Charcoal from Standard Type II, 2 Inch. Tray Adsorber Cello Engineered Safety Feature (ESF) Reset Controls NO YES YES Operability of ADS Valve Pneumatic Supply NO HO 01/17/80
/ /
NO 02/19/80
/ /
YES 03/19/80 03/19/80 YES 05/12/80 06/
,/81 LICENSEE SUBMITTED
RESPONSE
LICENSEE SUBMITTED
RESPONSE
UNCERTAIN OF THE EXACT DAY OF IMPLEMENTATIOH (6/81) 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 08 09 10 11 12 13 14 15 16 17 19 20 21 23 24 25 Examination of Containment Liner Penetration YES Welds Hydramotor Actuator Deficiencies HO Contamination of Nonradioactive System and YES Resulting Potential for Unmonitored, Uncontrolled Release to Environment Masonry Wall Design Decay Heat Removal System Operability Cracking in Core Spray Spargers Degradation of Scram Discharge Volume YES Capability Possible Loss of Emergency Notification YES System (ENS) with Loss of Offsite Power Potential Misapplication of HO Rooemount...Models 1151 and 1152 Pressure Transmitters with Either "A-or -D" Output Codes Failure of 76 of 185 Control Rods to Fully YES Insert During a Scram at a BWR Failures of Mercury-Wetted Matrix Relays in NO Reactor Protective Systems of...Plants Designed by Combustion Engineering Failures of Westinghouse Type W-2 Spring NO Return to Neutral Control Switches Valve Yokes Supplied by Malcolm Foundry NO
- Company, Inc.
Failures of Solenoid Valves Manufactured by HO Valcor Engineering Corporation Prevention of Damage Due to Water Leakage YES Inside 'Containment (October 17, 1980 Indian Point 2 Event)
Operating Problems with Target Rock YES Safety-Relief Valves at BWRs YES 06/09/80 06/09/&0 HO 06/09/80
/ /
YES 07/02/80 07/02/80 YES 07/25/80 07/25/80 YES 09/03/80 09/03/80 NO 07/28/80
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YES 09/02/80 12/27/80 HO 08/27/80
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NO 09/11/80
/ /
NO 01/14/81
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NO 12/03/80
/ /
YES 01/05/81 01/05/81 YES 10/14/87 10/14/87 YES 10/25/84 10/25/84 NO
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YES 05/16/80 05/16/80 LICEHSEE SUBMITTED
RESPONSE
PROGRAM ONGOING FOR INSPECTION AT EACH REFUELING OUTAGE HO FORMAL RESPONSE BACK LICEHSEE SUBMITTED
RESPONSE
SUBMITTED T.S.
CHANGE LICENSEE SUBMITTED
RESPONSE
LICEHSEE SUBMITTED
RESPONSE
LICENSEE SUBMITTED
RESPONSE
LICENSEE SUBMITTED
RESPONSE
Page Ho.
02/13/91 BL-s TITLE TABLE 1 HRC BULLETINS APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO HMPi REQUIRED DATE DATE COMMEHTS 81 02 03 s4 YEAR 82 82 01 82 03 04
++ YEAR 81 81 01 Surveillance of Mechancial Snubbers YES Alteration of Radiographs of Welds in Piping NO Subassemblies Stress Corrosion Cracking in Thick-Wall, Large Diameter, Stainless Steel,-
Recirculation System Piping at BWR Plants Deficiencies in Primary Containment HO Electrical Penetration Assembl.ies YES Failure of Gate Type Valves to Close Against NO Differential Pressure Flow Blockage of Cooling Water to Safety YES System Components by Corbicula Sp. (Asiatic Clam) and Mytilus Sp.
(Mussel)
YES NO YES NO NO NO 03/24/81 06/
/81 09/10/81
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05/22/81 05/22/81 06/23/82
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01/20/83
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LICEHSEE UNCERTAIN OF THE EXACT IMPLEMEHTATION DATE (6/81)
LICENSEE SUBMITTED
RESPONSE
LICENSEE SUBMITTED
RESPONSE
REPLACED BY GL 84-11.
SEE JUNE 29, 1984 LETTER LICENSEE SUBMITTED
RESPONSE
++ YEAR 83 83 01 83 02 03 Failure of Trip Breakers (Westinghouse DB-50) to Open on Automatic Trip Signal Stress Corrosion Cracking in large-Diameter Stainless Steel Recirculation System Piping at BWR Plants Check Valve Failures in Raw Water Cooling Systems of Diesel Generators NO YES YES HO YES YES
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06/14/83 12/
/83 REPLACED BY GL 84-11.
SEE JUNE 29, 1984 LETTER LICENSEE UNCERTAIN OF THE EXACT DAY OF IMPLEMENTATION (12/83) 83 83 83 83 04 05 06 07 08 Failure of the Undervoltage Trip Function of NO Reactor Trip Breakers ASME Nuclear Code Pumps and Spare Parte NO Manufactured by the Hayward Tyler Pump Company Nonconforming Materials Supplied by YES Tube-Line Facilities at Long Island City, HY, Houston,TX, A Carol Stream, IL Apparently Fraudulent Products Sold by Ray YES Miller, Inc.
Elect. Circuit Breakers With Undervoltage NO Trip...in Safety-Related Applications other than the Reactor Trip System NO HO YES YES NO
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06/15/83
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11/08/83 11/08/83 03/23/84 03/23/84 03/01/84
/ /
LICENSEE SUBMITTED
RESPONSE
LICENSEE SUBMITTED
RESPONSE
ss YEAR 84 84 01 84 02 Cracks in BWR Mark I Containment Vent Headers Failure of GE Type HFA Relays In Use In Class lE Safety Systems YES YES YES YES 09/17/84 09/17/84 07/12/84 04/26/86
Page Ho.
02/13/91 TITLE TABLE 1 HRC BULLETINS APPLICABLE RESPONSE
RESPONSE
IMPLEMEHTATION TO HMP1 REQUIRED DATE DATE COMMENTS 84 03 4+ YEAR 85 85 01 85 02 85 03 Refueling Cavity Water Seal Steam Binding of Auxiliary Feedwater Pumps Undervoltage Trip Attachments of Westinghouse DB-SQ Type Reactor Trip Breakers Motor-Operated Valve Common Mode Failures During Plant Transients Due to Improper S~itch Settings YES HO NO YES YES NO HO YES 11/26/84 11/26/84
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05/12/88 12/
/88 LICENSEE UNCERTAIN OF EXACT IMPLEMENTATION DAY w4 YEAR 86 86 01 86
'02 86 03 s+ YEAR 87 87 01 8I 02 Minimum Flow Logic Problems That Could Disable RHR Pumps Static "0" Ring Differential Pressure Switches Potential Failure of Multiple ECCS Pumps Due HO to Single Failure of Air-Operated Valve in Minimum Flow Recirculation Line NO NO Fastener Testing to Determine Conformance YES with Applicable Material Specifications Thinning of Pipe Walls in Nuclear Power YES Plants NO HO HO YES YES 06/06/86
/ /
07/29/86
/ /
11/13/86
/ /
09/14/87 06/
/90 07/25/86 07/25/86 LICENSEE SUBMITTED
RESPONSE
LICEHSEE SUBMITTED
RESPONSE
LICENSEE SUBMITTED
RESPONSE
ONGOING PROGRAM LICEHSEE UNCERTAIN OF EXACT DAY OF IMPLEMEHTATION (6/90).
88 88 88 88 88 Q3 04 05 07 08 Inadequate Latch Engagement in HFA Type YES Latching Relays Manufactured by General Electric (GE) Company Potential Safety-Related Pump Loss YES Nonconforming Materials Supplied by Piping YES
- Supplies, Inc....
and West Jersey Manufacturing Company Power Oscillations in Boiling Water Reactors YES (BWRs)
Thermal Stresses in Piping Connected to YES Reactor Cooling Systems 88 10 Nonconforming Molded-Case Circuit Breakers YES w4 YEAR 88 88 01 Defects in Westinghouse Circuit Breakers HO NO YES YES YES YES YES 03/28/88
/ /
07/14/88 07/14/88 05/09/90
/ /
09/09/88 09/09/88 02/01/89 11/14/89 09/29/88 06/ll/89 YES 10/30/89 02/11/91 LICENSEE SUBMITTED
RESPONSE
OPEH IMPI EMENTATION DATE HRC CLOSEOUT NUREG-1402 LICENSEE PROVIDED THE DATE 12/14/89, BUT DID HOT REFERENCE IT.
Page No.
5 02/13/91 BL-s TITLE TABLE 1 NRC BULLETINS APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO HMP1 REQUIRED DATE DATE COMMENTS 44 YEAR 89 89 02 Stress Corrosion Cracking of High-Hardness NO Type 410.. Bolting.. Anchor Darling S350H Swing Check Valves.. Similar NO 01/18/90
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LlCENSEE SUBMITTED
RESPONSE
++ YEAR 90 90 01 Loss of Fill-Oil in Transmitters Manufactured by Rosemount YES YES 07/20/90
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OPEH IMPLEMENTATION DATE AWAITING NRC APPROVAL 90 02 Loss of Thermal Margin Caused by Channel Box YES Bow YES 04/20/90 12/12/90
Page No.
02/15/91 TABLE 2 NRC GENERIC LETTERS ENCLOSURE 3 GL-s xxxxx APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REOUIRED D4TE D4TE COMMENTS T ITLE xaxxaa aaa aax aaxxa aaaxaa xaaaaaa a xa a
aaaaaaa aaaxaaaa aaaxaaxa
= aaaaxaa 79 79 18 19 79 20 79 21 79 22 23 79 79 25 79 26 79 27 79 28 31 79 79 79 ft YEAR 79 79 17 YES Reliability Of Onsite Diesel Generators 4t Light Water Reactors Westinghouse Two-Loop NSSS NO NRC Staff Review Of Responses To I()E YES Bulletins 79-06 and 79-06a Cracking In Feedwater Lines NO Enclosing NUREG/CR 0660, "Enhancement YES Of On Site Emergency Diesel Generator Reliability" Enclosing NUREG-0560, "Staff Report NO On The Generic 4ssessment Of Feedwater Transients In PWRs Designed By 86W NRC Staff Review Of Responses To 18E YES Bulletin 79'-08 Multiple Equipment Failures In NO Safety-Related Systems Information Required To Review YES Corporate Capabilities Upgraded Standard Technical YES Specification Bases Program Operability Testing Of Relief And NO Safety Relief Valves Evaluation Of Semi-Scale Small Break NO Experiment Transmitting NUREG-0473, Revision 2, YES Draft Radiological Effluent Technical Specifications Transmitting NUREG-0472, Revision 2, YES Draft Radiological Technical Spec ifications Submittal Of Copies Of Response To YES 6/29/79 NRC Request Transmitting NUREG-0578, "TMI-2 YES Lessons Learned" Transmitting NUREG-0576 - Security YES Training 4nd Oualification Plans New Physical Security Plans (FR NO 43280-285)
Regional Meetings To Discuss Impacts YES On Emergency Planning 4dequacy Of Station Electric YES Distribution Systems Voltages Amendment To 10 CFR 73.55 Deferral YES From 8/1/79 to 11/1/79 BWR Of f-Gas Systems Enclosing YES NUREG/CR-0727 NO NO YES NO NO YES YES NO YES NO
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08/10/79 08/10/79 09/13/79
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01/04/80 12/
/80 08/
/79 06/09/82 10/03/79 06/
/81 LICENSEE SUBMITTED RESPONSE LICENSEE UNCERTAIN OF THE EX4CT IMPLEMENTATION DATE LICENSEE UNCERTAIN OF THE EX4CT RESPONSE DATE (8/79)
LICENSEE UNCERT4IN OF THE EXACT IMPLEMENT4TION D4TE (6/81)
0
Page No.
02/15/91
~GL-S 5
TITLE 5555 555 5 5555 55 5555 5
11 5555 TABLE 2 NRC GENERIC LETTERS 4PPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REQUIRED DATE D4TE COMMENTS 5 S555555S 5
55 5 5 5
'SS11 555555S 11 5 5
5511 C
79 79 79 79 79 79 79 79 79 79 79 79 79 59 40 41 42 45 44 45 46 47 48 49 50 51 52 55 54 55 56 57 58 YES Transmitting Division 5 Draft NO Regulatory Guide 5 Value Impact Statement Follow-up 4ctions Resulting From The YES NRC Staf f Reviews Regarding The TMI-2 Accident Compliance With 40 CFR 190, EPA YES Uranium Fuel Cycle Standard Potential Unreviewed Question On YES Interaction Between Non-Safety Grade Systems Rnd Safety Grade Systems Reactor Cavity Seal Ring Generic NO Issue Referencing 6/29/79 Letter Re YES Multiple Equipment Failures Transmittal Of Reports Regarding YES Foreign Reactor Operating Experiences Containment Purging And Venting YES During Normal Operation Guidelines For Valve Operability Radiation Training YES Confirmatory Requirements Relating to YES Condensation Oscillation Loads For The Mark I Containment Long Term Program Summary Of Meetings Held On YES 9/18-20/79 To Disruss Potential Unrevidwed Safety Question On Systems Interaction For BttW Pl Emergency Plans Submittal Dates YES Follow-up Actions Resulting From The YES NRC Staff Reviews Regarding The TMI-2 4ccident Radioactive Release 4t North Anna YES Unit 1 And Lessons Learned ATWS YES Containment Purging 4nd Venting YES During Normal Operation Summary Of Meeting Held On October YES 12, 1979 To Discuss Responses To IE Bulletins79-05c Rnd HPI Termination Criteria Discussion Of Lessons Learned Short Term Requirements Rcceptance Criteria For The Mark I YES Containment Long Term Program ECCS Calculations On Fuel Cladding YES YES
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10/18/79 01/18/82 YES YES 10/23/79 10/23/79 10/09/79 10/09/79
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NO NO YES 11/01/90 05/01/80 YES YES ll/05/7'9 11/05/79 11/30/79 Ol/22/85 NO NO NO NO YES I
I I
I 08/08/85 07/24/84
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YES 11/16/79 09/
/80 YES 07/06/81 10/01/81 YES 11/30/79 01/22/85 NO IMPLEMENTATION DRTE REQUIRED RECENT 11/90
RESPONSE
SHOULD CLOSE OUT ITEM LICENSEE UNCERT4IN OF DAYS SEE GL 79 48 LICENSEE UNCERT4IN OF THE EXACT IMPLEMENTATION DATE (9/80)
Page No.
02/15/91 TABLE 2 NRC GENERIC LETTERS GL-¹ sasss 4PPLICABLE RESPONSE
RESPONSE
IMPLEMENT4TION TITLE TO NMP-1 REQUIRED D4TE DATE COMMENTS ssssas ass ssasasaaasassaaasaaaass aaaaaaaasa sa s
= assasasa saasss sass aa assaassa 79 79 79 79 59 60 61 62 GENERIC LETTER NEVER ISSUED Discussion Of Lessons Learned Short Term Requirements Discussion Of Lessons Learned Short Term Requirements EECS Calculations On Fuel Cladding NO YES YES NO YES
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11/16/79 09/
/80 LICENSEE UNCERTAIN OF THE EXACT IMPLEMENTATION DAY 79 79 79 79 79 79 63 64 65 66 67 68 69 70 Upgraded Emergency Plans YES Suspension Of 411 Operating Licenses YES Radiological Environmental Monitoring YES Program Requirements Enclosing Branch Technical Position, Revision 1
'4dditional Information RE 11/09/79 YES Letter On ECCS Calculations Estimates For Evacuation Of Various YES 4reas 4round Nuclear Power Reactors Audit Of Small Break LOCA Guidelines YES Cladding Rupture, Swelling 4 Coolant YES Blockage 4s 4 Result Of 4 Reactor Accident Environmental Monitoring For Direct YES Radiation NO NO NO NO YES NO NO
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02/01/80 02/01/80
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YEAR 80 80 80 80 80 80 80 80 80 80 80 80 001 002 003 004 005 006 007 008 009 010 011 YES YES YES YES YES NUREG-0630 " Cladding, Swel ling And Rupture Models For LOC4 Analysis" Ouality Assurance Requirements Regarding Diesel Generator Fuel Oil BWR Control Rod Failures IEB 80-01 Operability Of ADS Valve Pneumatic Supply IEB 79-Oib Environmental Oualification Of Class 1E Equipment Issuance Of NUREG-0313, Rev 1, "Technical Report On Material Selection And Processing Guidelines For BWR Coolant Pressur Information Regarding The Program For YES Environmental Oualification Of Safety-Related Electrical Equipment IEB 80-02 Inadequate Ouality Assurance For Nuclear Supplied Equipeent Low Level Radioactive Waste Disposal YES Issuance Of NUREG-0588, "Interim YES Staff Position On Equipment Qual ifications Of Safety-Related Electrical Equipment IEB 80-03 Loss Of Charcoal From YES Standard Type II, 2 Inch, Tray 4bsorber Cells YES NO NO NO NO NO NO NO NO 02/22/80 02/22/80
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pi
Page No.
02/15/91 GL-¹
=maraca TABLE 2 NRC GENERIC LETTERS 4PPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REOUI RED D4TE D4TE COMMENTS TITLE c ms+r Rr ssRRsr r ri s
'orrsrr'o'c RscorrxR sggkUBr;O'NN w
BRRr R R%%
ERR%
BRA r slit RRRSR NrwRRr Rr'0 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 YES 012 IEB 80-04 Analysis Of 4 PWR Main NO Steam Sine Break With Continued Feedwater 4ddition 013 Qualification Of Safety Related Electrical Equipment 014 LWR Primary Coolant System Pressure YES Isolation Valves 015 Request For Additional Management And YES Technical Resources Information 016 IEB 79-Olb Environmental YES Qualification Of Class 1E Equipment 017 Modifications To Boiling Water YES Reactor Control Rod Drive Systems 018 Crystal River 3 Reactor Trip From NO 4pproximately 100% Full Power 019 Resolution Of Enhanced Fission Gas YES Release Concern 020 4ctions Req..
From OL 4pplicants Of NO NSSS Designs By W and CE Resulting From NRC B&0 Task Force Review Of TMI2 Accident 021 IEB 80-05 Vacuum Condition Resulting NO In Damage To Chemical Volume Control System Holdup Tanks 022 Transmittal Of NUREG-0654 "Criteria YES For Preparation 4nd Evaluation Of Radiological Emergency
Response
Plans And Prepared 023 Change Of Submittal Date For YES Evaluation Time Estimates 024 Transmittal Of Information On NRC YES "Nuclear Data Link Specif ications" 025 IEB 80-06 Engineering Safety Feature YES (ESF) Reset Controls 026 Qualifications Of Reactor Operators YES 027 IEB 80-07 BWR Jet Pump 4ssembly
'ES Failure 028 IEB 80-08 Examination Of Containment YES Liner Penetration Welds 029 Modifications To Boiling Water YES Reactor Control Rod Drive Systems 030 Clarification Of The Term "Operable" YES 4s It Applies To Single Failure Criterion For Safety Systems Required By TS 031 IEB 80-09 Hydramotor 4ctuator YES Def iciencies 032 Information Request On Category I
NO Masonry Walls Employed By Plants Under CP and OL Review YES NO NO NO NO NO NO NO NO YES NO
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02I23/80 12/
/81
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05/20/80 02/02/84 LICENSEE UNCERTAIN OF THE EXACT DAY OF IMPLEMENATION LICENSEE SUBMITTED RESPONSE
Page No.
5 02/15/91 TABLE 2 NRC GENERIC LETTERS GL-N ROS$ 113 TITLE aeneas
=
a@a s-maaaez=
mesaaaec
=I:
APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REOUIRED DATE DATE COMMENTS Siiaaaaa=S=
aaaaaa=e mSaamaas
--=mmaarsax
=e aaasassar 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 033 Actions Req.
From OL Applicants Of NO B&W Designed NSSS Resulting From NRC B&0 Task Force Review Of TM12 Accident 034 Clarification Of NRC Requirements For YES Emergency Response Facilities At Each Site 035 Effect Of A DC Power Supply Failure NO On ECCS Performances 036 IEB 80-10 Contamination Of VES Non-Radioactive System And Resulting Potential For Unmonitored, Uncontrolled Release To Envir 037 Five Additional TMI-2 Related YES Requirement~
To Operating Reactors 038 Summary Of Certain Non-Power Reactor NO Physical Protection Requirements 039 IEB 80-11 Masonry Wall Design YES 040 Transmittal Of NUREG-0654 "Report Of YES The B&O Task Force"And 4ppropriate NUREG-0626 "Generic Eval Of FW Transient And Sbl 041 Summary Of Meetings Held On 4pril 22 YES
&23, 1980 With Representatives Of The Mark I Owners Group 042 IEB 80-12 Decay Heat Removal System NO Operability 043 IEB 80-13 Cracking In Core Spray YES Spargers 044 Reorganization Of Functions And NO Assignments Within ONRR/SSPB 045 Fire Protection Rule VES 046 Generic Technical Activity 4-12 YES Fracture Toughness 047 4dditional Guidance On "Potential For YES Low Fracture Toughness And Laminar Tearing On PWR SG
& Reactor Coolant Pump Suprts 048 Revision To 5/19/80 Letter On Fire YES Protection 049 Nuclear Safeguards Problems YES 050 Generic Activity A-10 BWR Cracks YES 051 On-Site Storage Of Low-Level Waste YES 052 Five Additional TMI-2 Related YES Requirements Erata Sheets To 5/7/80 Letter 053 Decay Heat Removal Capability NO NO
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NO
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I NO
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NO
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NO NO
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NO NO NO NO
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YES 06/20/80 03I
/81 MOST RECENT RESPONSE DATE USED LICENSEE UNCERT4IN OF D4Y OF IMPLEMENT4TION SEE
RESPONSE
TO IEB 80-11
Page No.
6 02/15/91 TABLE 2 NRC GENERIC LETTERS GL-s asa T I TLE rasa a sssaasaasaas asssrrsas sass APPLIC4BLE RESPONSE
RESPONSE
IMPLEMENT4TION TO NMP-1 REOUIRED D4TE DATE COMMENTS sass saras ssass assssass ssassssssssaas a ssasss 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 054 IEB 80-14 Degradation Of Scram NO Discharge Volume Capability 055 IEB 80-15 Possible Loss Of Hotline With Loss Of Off"Site Power 056 Commission Memorandum And Order On YES Equipment Oualification 057 Further Commission Guidance For Power YES Reactor Operating Licenses NUREG-0660 4nd NUREG-0694 058 IEB 80-16 Potential Misapplication Of YES Rosemount Inc. Models 1151/1152 Pressure Transmitters With "4" Or "D" Output Codes 059 Transmittal Of Federal Register YES Notice RE Regional Meeting~ To Discuss Environmental Oualification Of Elec. Equipment 060 Request For Information Regarding YES Evacuation Times 061 TMI-2 Lessons Learned NO 062 TMI-2 Lessons Learned YES 063 IEB 80-17 Failure Of Control Rods To YES Insert During 4 Scram At A BWR 064 Scram Discharge Volume Designs YES 065 Request For Estimated Construction YES Completion 4nd Fuel Load Schedules 066 IEB 80-17 Supplement 1 Failure Of YES Control Rods To Insert During A Scram At 4 BWR 067 Scram Discharge Volume YES 068 IEB 80-17 Supplement 2 Failures YES Revealed By Testing Subsequent To Failure Of Control Rods To Insert During A Scram 4t 4 069 IEB 80-18 Maintenance Of 4dequate NO Minimum Flow Through Centrifugal Charging Pumps Fol lowing Secondary Side Helb 070 IEB 80-19 Failures Of Mercury-Wetted YES Matrix Relays In RPS Of Operating Nuclear Power Plants Designed By GE 071 IEB 80-20 Failures Of Westinghouse YES Type W-2 Spring Return To Neutral Control Switches 072 Interim Criteria For Shift Staf fing YES 073 "Functional Criteria For Emergency YES Response Facilities",
NUREG-0696 074 Notice Of Forthcoming Meeting With YES Representatives Of EPRI To Discuss Program For Resolution Of USI 4-12, Fracture Tough NO NO NO NO YES YES NO YES NO YES NO YES NO NO NO NO NO 02/01/80 02/01/80
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09/17/80 04/13/81
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SEE
RESPONSE
TO IEB 80-15
'I
TABLE 2
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Page No.
7 02/15/91 NRC GENERIC LETTERS GL-S aeeee TITLE aeeaeaaaeaeaae eases eeaeaeeeaaeeeaee APPLIC4BLE RESPONSE
RESPONSE
IMPLEMENT4TION TO NMP-1 REQUIRED D4TE D4TE COMMENTS eeaeaae ea ceases a aaeeeeaa aaaeee eaaeaaa e
esses 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 075 Lessons Learned Tech Specs YES 076 Notice Of Forthcoming Meeting With GE YES To Discussed Proposed BWR Feedwater Nozzle Leakage Detection System 077 Refueling Water Level NO 078 Mark I Containment Long-Term Program YES 079 IEB 80-17 Supplement 3 Failures YES Revealed By Testing Subsequent To Failure Of Control Rods To Insert During A Scram At A 080 Preliminary Clarification Of TMI YES Action Plan Requirements 081 Preliminary Clarification Of TMI YES Action Plan Requirements Addendum To 9/5/80 Letter 082 IEB 79-01b Supplement 2 Environmental YES Qualification Of Class LE Equipment 083 Environmental Qualification Of YES Safety-Related Equipment 084 BWR Scram System YES 085 Implementation Of Guidance From USI YES A-12 "Potential For LOW Fracture Toughness And Lamellar Tearing On Component Support 086 Notice Of Meeting To Discuss Final YES Resolution Of USI A-12 087 Notice Of Meeting To Discuss Status YES Of EPRI-Proposed Resolution Of The USI 4-12 Fracture Toughness Issue 088 Seismic Qualification Of Auxiliary NO Feedwater Systems 089 IEB 79-Olb Supplement 3 Environmental YES Qualification Of Class LE Equipment 090 Post TMI Requirements, NUREG-0737 YES YES YES 091 Odyn Code Calculation 092 IEB 80-21 Valve Yokes Supplied By Malcolm Foundry Company, lnc.
093 Emergency Preparedness NO 094 Emergency Plan YES 095 Generic 4ctivity A-10 YES 096 Fire Protection YES 097 IEB 80-23 Failures Of Solenoid Valves YES Manufactured By Valcor Engineering Corporation 098 IEB 80-24 Prevention Of Damage Due To YES Water Leakage Inside Containment 099 Technical Specification Revisions For YES Snubber Surveil lance NO NO NO YES NO NO YES NO NO NO YES NO NO NO YES NO NO YES
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03/L3/85 09/01/85 SEE NRC BL79-018 SUPPLEMENT 2 SAVED AS NRC BL79-018 SUPPLEMENT 3 SEE GLs 82-85, 82-10, AND 89-06
Page No.
8 02/15/91 TABLE 2 NRC GENERIC LETTERS GL-¹ ss T ITLE as sssaaa saa asaaaasaaasaaassaassss APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REOUIRED D4TE D4TE COMMENTS ssaaaas aa ssaasss sasaaasa ssasaaaa a saa aaaaaaa 80 80 80 80 80 80 80 80 80 80 80 80 80 80 YES 100 4ppendix R to 10 CFR 50 Regarding Fire Protection-Federal Register Notice 101 Inservice Inspection Programs YES 102 Commission Memorandum And Order Of NO May 23, 1980 (Referencing IEB 79-Olb Supplement 2 - q.2 dc 3 Sept 30, 1980) 103 Fire Protection - Revised Federal YES Register Notice 104 Orders Qn Environmental Qualification YES Of Safety Related Electrical Equipment 105 Implementation Of Guidance For USI YES 4-12, Potential For Low Fracture Toughness And Lamellar Tearing On Component Supports 106 Report Qn ECCS Cladding Models, NO NUREG"0630 107 BWR Scram Discharge System YES 108 Emergency Planning YES 109 Guidelines F'r SEP Soil Structure YES Interaction Reviews 110 Periodic Updating Of FS4RS YES 111 IEB 80-17 Supplement 4, Failure Of YES Control Rods To Insert During 4 Scram 4t A BWR 112 IEB 80-25 Operating Problems With YES Target Rock Safety Relief Valves 113 Control Of Heavy Loads YES NO NO NO NO NO NO NO NO NO NO YES
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07/26/84 03I05/85 YEAR 81 81 81 81 Bl 81 YES YES YES 81 01 Qualification of Inspection, Examination, Testing and Audit Personnel 02
- Analysis, Conc 1usions and Recommendations Concerning Operator Licensing 03 Implementation of NUREG-0313, Technical Report on Material Selection(tc Processing GL For BWR Coolant Press Boundary Piping 04 Emergency Procedures And Training For YES Station Blackout Events 05 Information Regarding The Program For YES Environmental Qualification Of Safety-Related Electrical Equipment 06 Periodic Updating of Final Safety YES Analysis Reports (FSARS)
YES 07/30/81 07/31/81 NO YES 06/02/81 12/
/81 NO
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YES 07/06/81 07/07/81 SEE GL 88-01 LICENSEE UNCERT4IN OF THE EXACT DAY OF IMPLEMENTATION
Page No.
02/15/91 GL-s ss TITLE s ssaasaas asssaa
'sssass'a saaaas's's TABLE 2 NRC GENERIC LETTERS 4PPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NNP-I REQUIRED DATE DATE CONNENTS ssaasaaaaa saaaaasa asaassaa aasaaasa aa aa s s-as 81 81 81 81 81 81 81 81 81 81 81 81 81 81 81 81 Bi 81 81 81 81 81 81 Bi 07 08 09 10 12 16 17 18 19 20 21 22 23A 24 26 27 28 29 Control of Heavy Loads Odyn Code BWR Scram Discharge System Post-Tf(I Requirements For The Emergency Operations Facility BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619)
Fire Protection Rule (45 FR 76602>
11/19/80)
SER For GEXL Correlation For BXBR Fuel Reload Applications For 4ppendix D Submittals of The GE Topical Report Seismic Oualifications for Auxiliary Feedwater Systems Environmental Oualification of Class IE Electrical Equipment-Clarification of Staffs Handling of Proprietary Information NUREG-0737 Item I.C. 1 SER on Abnormal Transient Operating Guidelines (4TOG)
Functional Criteria for Emergency Response Facilities BWR Scram Discharge System-Clarification of Diverse Instrumentation Requirements Thermal Shock to Reactor Pressure Vessels Safety Concerns Associated With Pipe Breaks in The BWR Scram System Natural Circulation Cooldown Engineering Evaluation of The H.B.
Robinson Reactor Coolant System Leak on 1/29/Bl INPO Plant Specific Evaluation Reports INPO Evaluation Reports Nulti-Plant Issue 8"56 Control Rods Fail To Fully Insert Change in Implementing Schedule For Submission and Evaluation of Upgraded Emergency Plans Licensing Requirements for Pending Construction Permit and )fanufacturing License 4pplications Privacy and Proprietary Naterial in Emergency Plans Steam Generator Overfill Simulator Examinations YES YES YES YES YES YES YES YES YES NO YES NO YES YES YES YES YES YES YES NO YES NO NO NO YES YES NO NO YES NO NO NO NO NO NO NO NO
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11/29/82 03/01/83 10/22/84 04/01/85
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LICENSEE SUBMITTED RES'PONS'E
Page No.
02/15/91 10 TABLE 2 NRC GENERIC LETTERS GL-s TITLE rara aaraaaasaaa aa raraasa aaaaraa APPLICABLE RESPONSE
RESPONSE
IHPLEIfENTATION TO NI1P-1 REQUIRED DATE DATE COHNENTS r a arras saraaaaa aaarsar aarrrraasa
=- asraaa a
81 30 81 31 81 32 81 33 81 34 81 35 81 36 Bl 81 37 38 81 81 39 40 82 82 82 10 11 82 12 82 82 82 82 82 14 15 16 17 YEAR 82 82 01 82 02 82 03 82 04 82 05 82 06 82 07 Safety Concerns Associated With Pipe YES Breaks in the BWR Scram System Small Break LOCA Confirmatory NO Integral System~ Experiments for B5W Designed Plants NUREG-0737>
Item II.K.3.44-Evaluation YES of 4nticipated Transients Combined With Single Failure Technical Specification for Station NO Batteries Hultiplant 4ction Safety Concerns Associated With Pipe YES Breaks in the BWR Scram System Safety Concerns Associated With Pipe YES Breaks in the BWR Scram System Revised Schedule for Completion of YES TMI Action Plan Item II.D.1, Relief and Safety Valve Testing ODYN Code Reanalysi~
Requirements YES Storage of Low Level Radioactive YES Wastes at Power Reactor Sites NRC Volume Reduction Policy YES Qualifications of Reactor Operators YES New 4pplications Survey YES Commission Policy on Overtime YES High Burnup HAPLHGR Limits YES Use of INPO See-in Program YES Post-THI Requirements YES RTD Response Time Determination NO Transmittal of NUREG-0909 Relative to NO the Ginna Tube Rupture Transmittal of NUREG-0909 Relative to NO the Ginna Tube Rupture Environmental Qualification of Safety YES Related Electrical Equipment Post-THI Requirements YES Transmittal of NUREG-0916 Relative to NO the Restart of R.E. Ginna Nuclear Power Plant Nuclear Power Plant Staff Working YES Hours Reactor Operator and Senior Reactor YES Operator Examinations Submittal of Documents to the NRC YES Nuclear Plant Staff Working Hours NO NUREG-0737 Technical Specifications NO Inconsistecny of Requirements Between YES 50.54(T) and 50.15 YES NO NO NO YES NO NO NO NO YES NQ NO YES YES YES NO NO YES 11/12/81 11/12/81 01/25/82 01/25/82
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04/21/82 03/20/84 12/ 1 5/82 NRC EVALU4TION SEE GLs 82-12 AND 83-02 CONF IRN ORDER 08/31/82 TEL SEE GL 83-02, 04/25/83
RESPONSE
TECHNICAL SPECIFICATION 03/20/84
TABLE 2 Page No.
02/15/91 GL-S SRRSSR NRC GENERIC LETTERS APPLIC4BLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REQUIRED D4TE DATE COMMENTS TITLE arsmearrrrsrrsr sssasa s
=am:mrrs ss szsmaw ag=msa a s
===ma mrraas carresaassss=em asassaaas 82 82 82 82 82 82 82 82 82 82 82 82 82 82 82 82 82 82 82 82 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 34 35 36 37 38 39 Reactor Operator and Senior Reactor Operator Requalification Examinations Submittal of Copies of Documentation to NRC-Copy Requiremen ts for Emergency Plans and Physical Security Plans Guidance for Implementing the Standard Review Plan Rule Fire Protection 4udits Congressional Request for Information Concerning Steam Generator Tube Integrity Inconsistency Between Requirements of 10CFR 73.40(D) and Standard Tech Specs For Performing Audits of Sadeguards Contin Safety Relief Valve Quencher Loads:
BWR MARK II and III Containments Integrated 14EA Exercise for Physical Inventory at LWRS NUREG-0744, REV.
1 - Pressure Vessel Material Fracture Toughness Transmittal of NUREG-0763-Guidelines For Confirmatory In-Plant Tests of Safety-Relief Valve Discharge for BWR Plants Inadequate Core Cooling Instrumentation System NUREG/CR-2980 Filings Related to 10 CFR 50 Production and Utilization Facilities NUREG-0737 Technical Specifications Draf t Steam Generator Report (SAI)
Supplement 1 to NUREG-0737 Emergency
Response
Capabilities SECY 82-111 Modification of Vacuum Breakers 4 Mark I Containments Assignment of Authority to Regions for Nonpower Reactors Amendment~
and Licensing Activities NUREG-0737 Tech Specs Meeting to Discuss Developments for Operator Licensing Examinations Problems With Submittals of Subsequent Information of CURT 73.21 For Licensing Reviews YES NO YES YES NO YES YES YES YES YES NO NO YES NO NO YES NO NO NO YES YES NO YES NO NO NO NO NO YES NO 04/21/83 03/20/84
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Page No.
02/15/91 GL-s rrrrra 12 TITLE aaaaaa aaaaaa aaaraa aaraaaaaaaaaa TABLE 2 NRC GENERIC LETTERS 4PPLICABLE RESPONSE
RESPONSE
IMPLEMENT4TION TO NMP-1 REOUIRED DATE D4TE COMMENTS aaaaaa aaa aa aaaaa aaaaaaaa aa aaaaaaa a
rraaaaaa 83 83 02 03 04 05 83 06 83 83 07 08 09 as YEAR 83 83 01 Operator Licensing Examination Site Visit NUREG-0737 Technical Speci fications Regulatory Guide 1.150, "Ultrasonic Testing of Reactor Vessel Welds During Pre"Service and Inservice Examinations" Regional Workshops Regarding Supplement 1 to NUREG-0737, Requirements For Emergency
Response
Capability Safety Evaluation of "Emergency Procedure Guidelines, Revision 2rr June 1982 Certificates and Revised Format For Reactor Operator and Senior Reactor Operator Licenses The Nuclear Waste Policy 4ct of 1982 Modification of Vacuum Breakers on Mark I Containments Review of Combustion Engineering Owners'roup Emergency Procedures Guideline Program YES YES NO YES YES YES YES YES YES NO NO NO YES
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01/31/84 01/31/84
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03/07/86 03/07/86 83 83 83 10 104 10B LOC 10D LOE 10F 12 12A NO NO Resolution of TMI Action Item II.K.3'., "Automatic Trip of Reactor Coolant Pumps" Resolution of TMI Action Item NO II.K.3.5., "Automatic Trip of Reactor Coolant Pumps" Resolution of TMI 4ction Item NO II.K.3.5., "Automatic Trip of Reactor Coolant Pumps" Resolution of TMI 4ction Item NO II.K.3.5., "Automatic Trip of Reactor Coolant Pumps" Resolution of TMI 4ction Item NO II.K.3.5., "Automatic Trip of Reactor Coolant Pumps" Resolution of TMI 4ction Item NO I I.K.3.5., "Automatic Trip of Reactor Coolant Pumps" Licensee Oualification for Performing YES Safety 4nalyses in Support of Licensing 4c tions Issuance of NRC FORM 398 Personal YES Oualifications Statement Licensee Issuance of NRC FORM 398 Personal NO Dual ifications Statement Licensee
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Page No.
02/15/91 GL-s aaaa aaaaaaaaaaa aaaaa aaaaaa aaaaaaa TABLE 2 NRC GENERIC LETTERS APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REQUIRED DATE DATE COMMENTS aaaaaaaaaa aaaa aa aaaaaaa aaaaa aa aaaaa aaaaaaaa 83 83 83 83 13 14 15 16A 17 18 20 22 25 26 27 28 29 Clarification of Survell. Req's for NO HEPA Filters and Charcoal Absorber Units In STD. Tech Specs on ESF Cleanup Systems Definition of "Key Maintenance Personnel,"
(Clarification of Generic Letter 82-12 )
Implement. of Reg.
Guide 1.150, "Ultrasonic Testing of RX Vessel Welds During Preservice
& Inservice Examinations, REV. 1 Transmittal of NUREG-0977 Relative to YES the ATWS Events at Salem Generating Station, Unit NO.
1 Transmittal of NUREG-0977 Relative to YES YES YES YES YES YES the ATWS Events at Salem Generating Station, Unit NO.
1 Integrity of Requalification Examinations for Renewal of Reactor Operator and Senior Reactor Operator Licenses NRC Staf f Review of the BWR Owners'roup (BWROG) Control Room Survey Program New Procedures for Providing Public Notice Concerning Issuance of Amendments To Operating Licenses Integrated Scheduling for YES Implementation of Plant Modifications Clarification of Access Control YES Procedures for Law Enforcement Visits Safety Evaluation of "Emergency YES
Response
Guidelines" Safety Evaluation of "Emergency NO Procedure Guidelines" TMI Task Action Plan Item I.G.1, NO "Special Low Power Testing and Training," Recommendations for BWRS Issuance of NRC Form 398 Personnal NO Qualifications Statement - Licensee Clarification Of Surveillance NO Requirements For Diesel Fuel Impurity Level Tests Surveil lance Intervals in Standard YES Technical Specif ications Required Actions Based on Generic YES Implications of Salem ATWS Events This Generic Communication was not NO issued NO NO NO NO YES NO NO NO NO NO YES
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Page No.
02/15/91 GL->>
a r'r'a TITLE aassrrsaraaaasa aa arras r a saaars TABLE 2 NRC GENERIC LETTERS APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REOUIRED DATE DATE COMMENTS ra aaasra ars rara a arras aaarrssasaa
== saasssas C
83 83 83 83 83 83 83 83 83 YEAR 84 84 84 84 84 84 84 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 84 01 02 03 04 05 06 07 Deletion of STD.
Tech Spec NO Surveillance Requirement 4.8.1.1.2.d.6 For Diesel Generator Testing Safety Evaluation of "Abnormal NO Transient Operating Guidelines" NRC Staf f Recommendations Regarding Operator Action for Reactor Trip and ATWS NRC Positions on Certain Requirements YES of Appendix R to 10 CFR 50 Important to Safety NO Clarification of TMI Action Plan Item YES II.K.3.31 NUREG-0737 Technical Specif ications YES NUREG-0737 Technical Specifications NUREG-0965, "NRC Inventory of Dams" Voluntary Survey of Licensed Operators Operator Licensing Examination YES Fast Cold Starts of Diesel Generators YES Clarification to GL 81-07 Regarding YES
Response
to NUREG-0612, "Control of Heavy Loads at Nuclear Power Plants" Reporting Requirements of 10 CFR 50, YES Sections 50.72 and 50.73, and Standard Technical Specifications Availability of NUREG-1021, "Operator NO Licensing Examiner Standards" YES YES YES YES NRC Use Of The Terms "Important To Safety" and "Safety Related" Notice of Meeting Regarding Facility YES Staf fing Availability of NUREG-0933, "A
Prioritization of Generic Safety Issues" Safety Evaluation of W Topical NO Reports On Elimination of Postulated Pipe Breaks in PWR Primary Main Loops Change to NUREG-1021, "Operator YES Licensing Examiner Standards"
. Operator and Senior Operator License NO Examination Ct iteria For Passing Grade Proredural Guidance for Pipe NO Replacement at BWRs NO NO NO NO YES NO NO NO NO NO NO YES NO NO NO NO
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/86 12/
/86 01/31/84 10/29/84 LICENSEE UNCERTAIN OF EXACT DAYS
1
Page No.
02/15/91 GL-((
e'ea ea 15 aasaaaaaaaaeaaa asses s aaaaaaaasaaa TABLE 2 NRC GENERIC LETTERS 4PPLIC4BLE RESPONSE
RESPONSE
I)fPLENENTATION TO NNP-1 REQUIRED DAT'E DATE COMMENTS aesaeeaaaa assessee aaaaaaea aaaaaaeeeeea asaaaaaa 84 84 84 84 84 84 84 84 84 84 08 09 10 ll 12 13 14 15 16 17 18 19 20 21 22 23 Interim Procedures for NRC )fanagement YES of Plant-Specific Backfitting Recombiner Capability Requirements of YES 10 CFR 50.44(c)(3)(ii)
Administration of Operating Tests YES Prior to Initial Criticality Inspections of BWR Stainless Steel YES Piping Compliance M 10CFR61 and YES Implementation of Rad Effluent Tech
- Specs, Attendant Process Control Program Technical Specification for Snubbers YES Replacement and Requalif ication YES Training Program Proposed Staff Actions to Improve and YES (faintain Diesel Generator Reliability Adequacy of On-Shift Operating VES Experience for Near Term Operating License 4pplicants 4nnual )(ecting to Discuss Recent YES Developments Regarding Operator Training, Oualifications, and Examinations Filing of Applications for Licenses NO and Amendments 4vailability of Supplement 1 to YES NUREG-0933, "4 Prioritization of Generic Safety Issues" Scheduling Guidance for Licensee YES Submi tta 1 s of Reload~ That Involve Unreviewed Safety Questions Long Term Low Power Operation in NO Pressurized Water Reactors 10 CFR 20.408 Termination Reports
NO Format Reactor Vessel Mater Level YES Instrumentation in BWRs Cert of Compl to 10CFR50.49, Eq of YES Electric Equipment Important to Safety for Npps NO YES NO YES YES YES VES NO NO NO YES YES 07/31/84 03/01/84 10/18/88 07/0'9/89
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07/13/85 09/01/85 10/28/86 Ob/30/87 10/13/84 10/13/84
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I 03/10/89 03/10/89 01/23/85 03/31/85 YE4R 85 85 01 85 02 85 03 Fare Protectxon Polzcy Steering Committee Report Staff Recommended Actions Regarding Steam Generator Tube Integrity Clarification of Equivalent Control Capacity for Standby Liquid Control Systems YES YES NO
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TABLE 2 Page No.
02/15/91 GL-Ã asssss 16 TITLE asass saaasa s
= sass aaaaaaasaasaas NRC GENERIC LETTERS APPLICABLE RESPONSE
RESPONSE
IlfPLEIfENTATION TO NAP-1 REOUI RED DATE DATE COMMENTS asaasssasa aaa sass ar asaas as aassas a a saaaaa 85 85 85 04 05 06 Operating Licensing Examinations Inadvertent Boron Dilution Events Duality Assurance Guidance for ATWS Equipment That Is Not Safety-Related YES NO NO NO NO
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10/10/85
/ /
LICENSEE SUBMITTED RESPONSE IlfPLENENTED THROUGH REOUIRENENTS OF 10CFR50
~ 62 85 85 85 85 85 85 85 85 85 85 85 07 21 08 09 10 11 12 13 14 15 16 17 18 19 20 22 YES YES Implementation of Integrated Schedules for Plant Nodifications 10 CFR 20 '08 Termination Reports Format Technical Specifications For Generic NO Letter 83-28, Item 4.3 Technical Specification For Generic NO Letter 83-28, Items 4.3 and 4.4 Completion of Phase II of "Control Of YES Heavy Loads At Nuclear Power Plants" NUREG-0612 Implementation Of TMI Action Item YES I I.K.3.5, "Automatic Trip Of Reactor Coolant Pumps Transmittal Of NUREG-1154 Regarding YES The Davis-Besse Loss Of Ifain And Auxiliary Feedwater Event Commercial Storage At Power Reactor YES Sites Of Low Level Radioactive Waste Not Generated By The Utility Information On Deadlines For YES 10CFR50.4'9, "EO Of Electric Equipment Important To Safety At Npps" High Boron Concentrations YES Availability Of Supplements 2 and 3
YES Yo NUREG-0933, "A Prioritization Of Generic Safety Issues" Operator Licensing Examinations YES Reporting Requirements On Primary NO Coolant Iodine Spikes Resolution Of Generic Issue 69:
High NO Pressure Injection/l1ake-up Noz z Ie Cracking In Babcock And Wilcox Plants This Generic Communication was not NO issued Potential For Loss Of Post-LOCA YES Recirculation Capability Due To Insulation Debris Blockage NO NO NO NO NO NO NO NO NO
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YEAR 86 86 01 86 02 Safety Concerns Associated With Pipe YES Breaks In The BWR Scram System Technical Resolution of Generic Issue YES 8 Thermal Hydraulic Stability NO NO
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TABlE 2 Page No.
02/15/91 17 NRC GENERIC LETTERS GL-S a
sss APPLICABLE RESPONSE
RESPONSE
IMPLEMENT4TION TITLE TO NMP-1 REOUIRED DATE DATE COMMENTS sssaa asaasass aasaesaeass saaaass-saa aaasaaesaa sasaaaas saasssas saaasssssaass sasssaes 86 86 86 86 86 86 86 86 86 86 Bb Bb 86 03 04 05 06 07 08 09 10 11 12 13 14 15 16 17 YES YES YES YES Applications For License Amendments Policy Statement On Engineering Expertise On Shift Implementation Of TMI 4ction Item NO II.K.3~ 5, "4utomatic Trip Of Reactor Coolant Pumps" Implementation Of TMI 4ction Item NO II;K~ 3.5, "4utomatic Trip of Reactor Coolant Pumps" Transmittal of NUREG-1190 Regarding The San Onofre Unit 1 Loss of Power And Water Hammer Event 4vailabi lity of Supplement 4 to NUREG-0933, "4 Prioritization of Generic Safety Issues" Technical Resolution of Generic Issue YES 8-59, (n-1) Loop Operation in BWRs and PWRs Implementation of Fire Protection YES Requirements Distribution of Products Irradiated NO in Research Reactors Cr iteria for Unique Purpose Exemption NO From Conversion From The Use of Heu Fuel Potential Inconsistency Between Plant NO Safety Analyses and Technical Specifications Operator Licensing Examinations YES Info... Compliance W 10CFR50.49 "Eq YES of Electric Equipment Important to Safety For Nuclear Power Plants" Westinghouse ECCS Evaluation Models NO Availability of NUREG-1169, YES "Technical Findings Related to Generic Issue C-B, BWR MSIC Leakage 4nd Treatment Methods" NO NO NO NO NO YES NO NO
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06/01/88 06/01/88 YEAR 87 87 01 87 02 87 03 87 04 Public Availability Of The NRC Operator Licensing Examination Ouestion Bank Verification of Seismic Adequacy of Mechanical and Electrical Equipment In Operating Reactors (USI 4-46)
Verification of Seismic Adequacy of Mechanical and Electrical Equipment In Operating Reactors (USI 4-46)
Temporary Exemption From Provisions Of The FBI Criminal History Rule For Temporary Workers YES YES YES NO YES NO NO
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11/30/87
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SEE 13/19/90 NRC LTR OPEN IMPLEMFNATION D4TE
Page No.
02/15/91 GL-S saaasa TITLE saassasaaaaaasaas-aaaa aaaaaaa sass TABLE 2 NRC GENERIC LETTERS APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REQUIRED DATE D4TE COMMENTS assasss s-sass
=== aasasass asassaaasassaa aa aasa 87 87 87 87 87 87 87 87 87 87 87 05 06 07 08 10 11 12 13 14 15 16 Rqst Add I Info Assessment Degradation Of Mark I Drywells Periodic Verification Of Leak Tight Integrity Of Pressure Isolation Valves Information Transmittal of Final Rulemaking For Revisions
'To Operator Licensing 10 CFR 55 4nd Conf irming 4mendments Implementation of 10 CFR 73.55 Miscellaneous 4mendments and Search Requirements Sections 3.0 4nd 4.0 of Standard Tec Specs on Limiting Conditions For Operation 4nd Surveillance Requirements Implementation of 10 CFR 73.57, Requirements For FBI Criminal History Checks Relaxation in Arbitrary Intermediate Pipe Rupture Requirements Loss of Residual Heat Removal While The Reactor Coolant System is Partially Filled Integrity of Requalification Examinations At Non-Power Reactors Operator Licensing Examinations Policy Statement On Deferred Plants Transmittal of NUREG-1262, "4nswers To Questions On Implementation Of 10 CFR 55 On Operators'icenses" YES YES YES YES YES YES NO NO YES YES YES YES YES NO NO NO NO NO NO 06/26/90 06/26/90 04/26/87 06/27/87
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88 02 03 88 04 88 05 06 88 07 YE4R 88 88 01 YES NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping Integrated Safety Assessment Program YES II (ISAP II)
Resolution of Generic Safety Issue NO 93, "Steam Binding of 4uxiliary Feedwater Pumps" Distribution of Gems Irradiated In NO Research Reactors Boric 4cid Corrosion of Carbon Steel NO Reactor Pressure Boundary Components In PWR plants Removal Of Organization Charts From YES Technical Specification 4dministrative Control Requirements Modified Enforcement Policy Relating YES to 10 CFR 50.09, "Environmental Cualification Of Electrical Equipment Important To YES NO 11/02/90 09/04/90
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02/15/91 GL-S a 's a s 19 TITLE aaas aaaaaaaaaaaa aaaaaaaaaaaaaaaaaa TABLf 2 NRC GENERIC LETTERS APPLICABLE RESPONSE
RESPONSE
IMPLEMENTATION TO NMP-1 REOUIRED DATE D4TE COMMENTS asar aaaaa a
aa aaaaaa a aaaaaaaaaaa
-= aaaaaaaa 88 88 88 BB 88 88 88 88 88 88 88 88 88 08 09 10 11 12 13 14 15 16 17 18 19 20 20 20 20 Initiation Of The Individual Plant Examination For Severe 4ccident Vulnerabi1ities - 10 CFR 50.54 4ccident Nanagement Stratagies for YES Consideration in the Individual Plant Examination Process Completion of Containment Performance YES Improvement Program and Forwarding of Insights for Use in the IPE for S4V YES Mail Sent or Delivered To The Office YES Of Nuclear Reactor Regulation Pilot Testing of Fundamentals YES Examination Purchase of GSA Approved Secur ity YES Containers NRC Position on Radiation YES Embrittlement Of Reactor Vessel Materials And Its Impact On Plant Operations Removal of Fire Protection YES Requirements From Technical Specification Operator Licensing Fxaminations YES Instrument 4ir Supply System Problems YES 4ffecting Safety-Related Equipment Electric Po~er Systems Inadequate YES Control Over Design Process Removal Of Cycle-Specific Parameter YES Limits From Technical Specifications Loss of Decay Heat Removal NO Plant Record Storage On Optical Disks YES Use Of Deadly Force By Licensee NO Guards To Prevent Thef t Of Special Nuclear Naterial Individual Plant Examination For YES Severe Accident Vulnerabilities NO NO YES
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11/22/88
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NO
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NO NO YES 11/05/89
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YES 11/05/89
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YES 11/05/89
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YES 1 1/05/89
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NO
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YES 04/10/89
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4 T.S.
CHANGE TO RESOLVE PLANNED REQUIRED FOR 1992 RO INPLEN.
DATE OPEN LICENSEE 4/1/89
RESPONSE
PROVIDED SCHEDULE FOR COMPLETION OF WORK BY1992 RO INCORPOR4TED IN SECURITY
- PL4N, NO IMPLENENATION DATE REOUIRED IPE/EP I IMPLENENT4TION TIED TO DESIGN BASIS RECONSTITUTION PROGRAM I
PE /EP I IMPLEMENT4TION TIFD TO DESIGN BASIS RECONSTITUTION PROGRAN I PE IEP I IMP LENENTAT ION TIED TO DESIGN B4SIS RECONSTITUTION PROGR4N IPE/EP I INPLEMENTATION TIED TO DESIGN BASIS RECONSTITUTION PROGR4M YEAR 89 89 01 89 02 04 Implementation Of Programmatic And YES Procedural Controls for Radiological Effluent Technical Specifications Actions To Improve The Detection Of YES Counterfeit And Fraudulently Marketed Products Operator I icensing National YES Examina tion Schedule Guidance On Developing Acceptable YES Inservice Testing P'ograms NO NO NO
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Page No.
02/15/91 20 TABLE 2 NRC GENERIC LETTERS GL-¹ TITLE APPLIC4BLE RESPONSE
RESPONSE
IMPLEMENT4TION TO NMP-1 REQUIRED DATE DATE COMMENTS aa aaaaassaa aaaaaa aassaa aaaa aaaaa aaaaa aaa aaaas:aa aa aaaaa a
aaaaaa a
89 89 89 89 89 05 06 07 08 09 10 YES YES Pilot Testing Of The Fundamentals Examination Task Action Item I.D.2 - Safety Parameter Display System 10 CFR 50.54 (f )
Power Reactor Safeguards Contingency YES Planning For Surface Vehicle Bombs Erosion/Corrosion-Induced Pipe Wall YES Thinking 4SME Section III Component YES Replacements Safety-Related Motor-Operated Valve YES Testing 4nd Surveillance NO YES YES YES NO YES
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07/ll/89 07/11/89 11/07/89 11/07/89 07/05/89 07/05/89
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10/10/90
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NMPC DEVELOPING PROGRAM PLAN TO ADDRESS RECOMMEND OF GL IMPLEM. D4TE OPEN 89 89 89 89 11 12 13 14 15 16 Resolution Of Generic Issue 101 "Boiling Water Reactor Water Level Redundancy" Operator Licensing Examination Service Water System Problems 4ffecting Safety-Related Equipment Line-1 tee Improvements In Technical Specifications - Removal Of 3.25 Limit On Extending Surveil lance Intervals Emergency
Response
Data System Installation Of 4 Hardened Wetwell Ven t YES YES YES YES YES YES NO NO YES NO NO YES
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12/07/90
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ll/30/90 01/11/91
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10/15/90
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4CTIONS REQUIRED TO BE COMPLETED BY 1992 REFUELING OUT4GE IMPLEM. DATE OPEN LICENSEE SUBMITTED RESPONSE 4CTIONS TO BE COMPLETED IN 1992 REFUELING OUTAGE IMPLEMENTATION D4TE OPEN 89 89 89 89 89 89 89 17 18 20 21 22 23 YES YES Planned 4dministrative Changes To The NO NRC Operator Licensing Written Examination Process Resolution Of Unresolved Safety Issues A-17, "Systems Interactions In Nuclear Power Plants" Request For Actions Related To Resolution Of Unresolved Safety Issue A-47s
~ ~
s Pursuant To 10 CFR 50.54(f)
Protected Area Long-Term Housekeeping NO Status Of... Unresolved Safety YES Issue Requirements Potential For Increased Roof YES Loads...Due To Recent Change In Probable Maximum Precipitation Criteria...
NRC Staff Responses To Questions YES Pertaining To Implementation Of 10 CFR Part 26 NO YES YES NO NO
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05/04/90 05/04/90
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11/25/89 08/28/89
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Page No.
21 02/15/91 TABLE 2 NRC GENERIC LETTERS GL->>
~Iaaa TITLE aa aaaaaaaa aaaaaaaaaaaa a aaaaaaaa a
APPLICABI E RESPONSE
RESPONSE
IMPLEMENT4TION TO NMP-1 REQUIRED DATE D4TE COMMENTS aaaaaa aa aaaaa aa aaaaaaaa aaaaaa aaaaaaa a
aaaaa 90 03 90 04 05 06 90 07 90 90 08 09 SS YEAR 90 90 01 90 02 Request for Voluntary Participation YES in NRC Regulatory Impact Survey Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications Relaxation of Staf f Position in Generic Letter 83-28, Item 2.2 Part 2 "Vendor Inter face for Sa fety-Related Components" Request for Information on the Status YES of Licensee Implementation of GSIs Resolved With Imposition of Requirements or CAs Guidance for Performing Temporary YES Non-Code Repair of ASME Code Class 1,
2, and 5 Piping Resolution of Generic Issues 70, NO "PORV and Block Valve Reliability,"
and 94, "Additional LTOP Protection for PWRs" Operator Licensing National YES Examination Schedule Simulation Facility Exemptions YES Alternative Requirements for Snubber YES Visual Inspection Intervals and Corrective 4ctions NO NO YES NO NO NO NO NO
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09/25/90
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FORMAL VENDOR INTERF4CE PROGRAM BEING DEVELOPED DURING 1991 IMPLEM. OPEN YEAR 91 91 01 Removal of the Schedule for the Withdrawal of Reactor Vessel Material Specimens From Technical Specif ications YES
S I