ML20030B486
| ML20030B486 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/14/1981 |
| From: | Hovey G METROPOLITAN EDISON CO. |
| To: | Snyder B Office of Nuclear Reactor Regulation |
| References | |
| LL2-81-0196, LL2-81-196, NUDOCS 8108180182 | |
| Download: ML20030B486 (24) | |
Text
{{#Wiki_filter:,- Metropolitan Edison Cornpany Post Office Box 480 Middletown, Pennsylvania 17057 Writer's Direct Dial Number August 14, 1981 LL2-81-0196 i I TMI Program Office / g p Attn: Dr. B. J. Snyder, Program Director /S k f I U. S. Nuclear Regulatory Commission p /*U g J7 c/o Three Mile Island Nuclear Station v.a. g****gN Middletown, Pennsylvania 17057 =, *
- P o
Dear Sir:
q Three Mile Island Nuclear Station, Unit 2 (TMI-2) Cu % Operating License No. DPR-73 Docket No. 50-320 NBC letter of 5/4/81 - Generic Letters This letter is a partial response to your letter of May 4, 1981. Attached are two tables which identify all generic letters you have proposed as being apparently applicable to TMI-2 (Table 1)* and those that, given the present condition of TMI-2, you designated apparently not applicable (Table 2). The attached Table 3 provides a listing of the generic letter items that either remain to be evaluated for applicability or response is being prepared. All other items have been either responded to or judged that no additional response is required. We have concluded our evaluation of a substantial number of the entire list of generic letters you identified in your May 4, 1981 letter. This evaluation concluded that these letters can be characterized in the following manners: (1) Letters specifically responded to on TMI-2 that close out our response (including common TMI-1 and TMI-2 letcers). The transmittal letter and date are provided for your reference. (2) Letters specifically responded to on the TMI-l docket that are fully applicable and close out our response on TMI-2. The transmittal letter on TMI-l is identified under TMI-l docket applicable correspondence. (3) Letters responded to on the TMI-l docket that constitute a portion of the TMI-2 response. Transmittal letter on TMI-1 are identified in the column entitled TMI-l docket applicable correspondence. 1 '\\
- Includes 3 items identified by NRC subsequent to letter of May 4, 1981.
8108180182 810814 PDR ADOCK 05000320 P PDR wwopohtan Ed: son Company is a Member of the General Pubhc Ut. lit.es System
Dr. B. J. Snyder LL2-81-0196 (4) Letters currently under evaluation or response preparation. (5) Letters not applicable to TMI-2 regardless of operating mode, and letters which do not require a Licensee response by virtue of the NRC letter or subject. Such letters are designated no response required. (6) Letters which require or may require evaluation on TMI-2. Such letters do not have entries or are designated to be currently under evaluation or response preparation. (7) Letters which have not been received or cant.ot be located. Separate telephone requests have been made te the NRC for these letters. (8) Letters which GPU concurs are not applicable to TMI-2 in the recovery mode. Such letters are designated not applicable. Where indicated on Table 3 evaluation is not yet complete. At the conclusion of this applicability evaluation all applicable items not previously responded to will undergo evaluation and a response to the NRC vill be prepared. We are continuiag our assessment and will update the attached list in two months at which time we anticipate all items will either be responded to, determined unapplicable, or under evaluation or response preparation on TMI-2. Sincerely, . K. Hovey Vice-President and Director, TMI-2 GKH:WJM:djb Attachment ec: L. H. Barrett, Deputy Program Director
Pcge 1 of 6 Table 1 Items NRC identified as apparently applicable to TMI - 2 I l 1 IMI-l docket l No (1)l l Abbreviated I TMI-2 applicable l applicable l Response l l Subject l Correspondence ! Correscondence l Required l Comments l I 1 1 6/4/79 l NUREG/CR 0660 l l l X l I" Enhancement of I l l l l Onsite Emergency l l l l 1 Diesel Generator l l l l l Reliability" l l l l 1 l i i I 6/29/79 l Corporate l TLL-700 / GQL979 l 1 l Referenced correspondence identifies manage-l LaprJJilities l 12/31/80/ 8/10/79 l l l ment and technical response resources. I l l l l 7/30/79 l NUREG-0576 1 1 l X l I" Security Training I i l 1 I and Qualifications! I l l l Plans" l l l l 1 I l l l 8/3/79 l Regional meetings ! l l X l Regional meetings we attended by GPUN l on emergency l l l l personnel. I planning l l l l 1 1 I I l 8/8/79 l AdegJacy of I lGQL-0997 7/22/77)
1 Under evaluation.
I Station Electric l lGQL-1145 8/9/77 l l l Distribution l lTLL-224 5/15/80 l l l System Voltages l lTLL-543 11/7/80 l l I l l 1 1 8/10/79 l Amendmeat to 10 1 l 1 l Licensee's Security Plan Addresses 73.55 l CFR 73.55 deferrall i l requirements. I from 8/1/79 to l l l l l 11/1/79 l l l l l 1 1 I I 9/17/79 l Compliance with 40l GQL-1390 11/6/79 l l l l CFR 190, EPA l 1 l l l Uranium Fuel Cyclel l l l l Stanoard l l l l l 1 I l l 9/25/79 l Transmittal of I l l l Awaiting receipt of letter. l Reports Regarding i i l l l Foreign Reactor l l l l l Operating l l l l l Experiences I l l I I I I i
Page 2 of 6 Table 1 Items NRC identified as apparently applicable to TMI - 2 I I l TMI-1 docket l No (1)l l Abbreviated l TMI-2 applicable l applicable l Response l l Sut, ject l Conespondence Correspondence l Required l Comments 1 I I I 10/2/79 l Radiation Trainingl l l l l 1 1 I i 10/10/79 I Emergency Plans l TLL-700 l I X l Referenced correspondence submitted the I submittal dates l 12/31/80 l l l TMI -2 E. Plan. l I l l l 10/17/79 l Radioactive l l l l Under evaluation. I Release at North l l l l l Anna Unit 1 and l l l l l Lessons Learned l l l l l l l l l l TSCR 34A l 1 Unit 1 correspondence applicable to TMI-2 11/27/79 l Radiological l l Environmental l l TLL-493 l l l Monitoring Programl l 10/3/80 l l l Requirements l l l l l BTP, Rev. 1 l l l l 1 l l l l 11/29/79 l Estimates for l l LIL-083 l l Referenced correspondence submitted requested l Evacuation of l l 3/30/81 l l Evacuation Time Estimates. I various areas l l LIL-145 l l l Around Nuclear l l 5/15/81 l l l Power Reactors l l l l l 1 l 1 l l l X l 12/21/79 l Proposed Rule on l l Radiological l l l l l Emergency Responsel l l l l Plans l l l l l l l l 1/7/80 l Quality Assurance l l TLL-164 l l Under evaluation. l Requirements l l 4/8/80 l l l Regarding Diesel l l l l l Generator Fuel 0111 l l l 1 I I l l l NRC telephone convere,ations withdrew this 1/29/80 i Low level l l l Radioactive l l l l letter. I Waste Disposal l l l l I I I l l l 3/10/80 l IEB 80-05 Vacuum l TLL-381 l 1 l Condition Result-l 8/22/80 l l l l l l l l l4
Page 3 of 6 Table 1 Items NRC identified 93 apparently apolicable to TMI - 2 I I I TMI-l docket I No (1)j l Abbreviated i TMI-2 applicable I applicable l Response l l Subject l Correspondence i Corresoondence I Required I Comments 1 I I I I (con't) I ing in Damage to I (see previous l l l l Ctemical Volume i p age) l l l l Control System i i l 1 1(CVCS) Holdup Tanksi i l l I l l l 1 3/10/80 1 Emergency Planning! TLL-700 1 l l Referenced correspondence transmitted the l Transmitting I 12/31/80 I I l TMI-2 radiological response plan. I NUREG-0654 for l I l I I Interim Use and i I i l l Comment i I I I I I I I I 3/28/80 l Qualifications of l TLL-483 l l - - - - - - - l Unit 2 training programs reflect status of I Reactor Operators l l l l Unit 2 systems. 10/7/80 I i l I l 4/10/80 l Operability of i I 1
1 Item is N. A. Recovery Tech Specs specify I dystems I
l l l operable requirements for Recovery Mode. I I I I I 5/7/80 l Five Additional l See Comments I l l All items were incorporated into NUREG 0737. I TMI-2 Related l l l l l Requirements to l l I l l Operating Reactorsl l l l 1 I I I I 5/8/00 l IEB 80-11 Masonry l l l I Response under preparation. I Wall Design l l I l l l l I 1 5/19/80 l Fire Protection l l l X l l Rule (Draft) l l l i i i I I I 5/22/80 l Fire Protection 1 l I X l 1 Rule revised pagesl l l I l to 5/19/80 letter l l l 1 1 I I I i 6/9/80 l Errata Sheets to l See Comments I I
l All items were incorporated into NUREG 0737.
l May 7 letter on l l l l 1 five additional l l l l l THI-2 related l l l l l requirements. l l l l 1 1 I I I I I I I I
Page 4 of 6 -Table 1 Items NRC identified as apparently applicable to TMI - 2 l I l TMI-l docket l No (1)l l Abbreviated l TMI-2 applicable I applicable l Response I l Subject l Correspondence l Correspondence i Required l Comments l I I I I l l Referenced correspondence addressed both j 6/18/80 l IEB 80-15 Possible! TLL-558 I TLL-558 l 1 l Loss of Hotline 1 10/31/80 l 10/31/80 l l TMI-l and 1MI-2. l Hotline with Loss l l l l l of Off-Site Power l l l l 1 1 I I i l T l l 6/25/80 l Memorandum and 1 l Order dated May 271 l l I i 1980, re fire l l l l l protection for l l l l l electrical cables,I l l l l and environmental l l l l l qualification of I i l l i electrical l l l l I components l l l l l 1 l l I l l l 7/31/80 1 IEB 80-20 Failures! TLL-484 l I I of Westinghouse l 3/30/80 l l l l Type W-2 Spring i l l l Return to Neutral l l l l l Control Switches i l l l I I I I l l This criteria is not applicable to TMI-2 I l 7/31/80 l Interim Criteria l See Comraents 1 l for Shift Staffingl i l I recovery mode 7. See TMI-2 technical spec. I I I I i l X l See 3/5/81 item. l 8/1/80 I" Functional l I Criteria for l I i l l Emergency Responsel l l l l Facilities l l l l l NUREG-0696 I l l l I I I I I 11/6/80 l IEB 80-21 Valve l TLL-682 l 1 I l yokes supplied by 1 12/29/80 l l l l Malcolm Foundry l l l l l Cocpany, Inc. i l l Report on inspec-l l l l l tion and correct-1 I l l I ive actions con-l l i i i cerning Malcolm i l l l l valve yokes l l l l
Page 5 of 6 Table 1 Items NRC identified as apparently molicable to TMI - 2 l l l TMI-l docket l No (1)l l Abbreviated 1 TMI-2 @plicable I applicable l Response l l Subject l Correspondence l Correspondence i Required l Comments l 1 I I i j I Noted correspondence submitted E. Plan and l 11/13/8C l Emergency Plan l TLL-70012/31/80 l l lLL2-81-0059 2/27/811 l l E. Plan Inplementing Procedures. j j l l l l l 1 11/14/80 i Fire Protection l See 11/24/80 item l l l l l l 1 l 11/14/80 l IEB 80-23 Failures l TLL-658 l l of Solenoid Valvesl 12 /12 /80 l l l l Engineering Corp. I l l l l I I I I l Response under preparation. 1 11/24/80 l Appendix R to 10 lLL2-81-0084 3/24/811 I CFR 50 re. Fire 1 5/7/81 Snyder to l l l l Protection I Hovey l l l 1 1 1 I I l 11/25/80 l Containment Struc-l l l l Awaiting receipt of letter. I tures Inservice i l l I l Inspection Programl l l l l l l l l 1 l . 11/25/80 l Fire Protection i see 11/24/80 item l I I I I I I l NUREG-0654 was utilized in developing l 12 /9/8 0 l Emergency Planning l TLL-700 l LIL-083 1 i NUREG-0654, Rev. Il 12/31/80 1 3/30/81 l l Licensee's Radiological Response Plan for I and 2 summary l l LIL-145 l l TMI-2. Evacuation time estimates were sub-I rating sheets for i 1 5/15/81 I mitted by the referenced TMI-l correspondence I evacuation time l l l l l estimates l I l l l 1 I I l1 Referenced correspondence requested exemption 1 12/15/80 i Periodic updato l LL2-81-Oll4 l i of FSARS l 5/6/81 l l l from 50.71(e) Regulatory Requirements. I I I I i l X l 1 1/27/81 l Operator Licensing 1 l 1 I l l i I I I Il Staffing levels-see TLL-700, NUREG 0696 see. 2 /18/8 1 l Emergency Opera-l TLL-7M l LIL-175 l I tions Facility 1 12 /i. 8 0 l 6/10/81 l l 3/5/81 item. I l l l ll Response under preparation. 2/20/81 l Fire Protection lLL2-81-0084 3/24/81l l I Rule 1 5/7/81 Snyder to l l l l l Hovey l l l l l I l I nn
Page 6 of__6 Table 1 Items NRC identified as apparently applicable to TMI - 2 l l l TMI-l docket l No (1)l l Abbreviated l TMI-2 applicable I applicable l Response l l Subject I Correspondence l Correspondence l Required 1-Comments 1 I I I I 2/25/81 l Emergency l l l l l Procedures and I l l l l Training for l l l l l Station Blackout l l l l l Events l l l l l l l l i 2 /26/81 l Periodic Updating l LL2-81-0114 l l l Referenced correspondence requested exemption I of Final Safety l 5/6/81 l l l from 50.71(e) Regulatory Requirements. l Analysis Reports l l l l l (FSARS) l I l l l l l l l 3/5/81 1 Emergency Resp. l l LIL-175 1 l Further information will be provided per l Facility l l 6/10/81 I I referenced correspondence. l (NUREG-0696) l l l 1 1 1 I I l 6/19/81 l ENS. System l LL2-0185 7/28/81 l I I Stpplemental response under prepmation. I I I I I 7/1/81 l Prompt l Lll-214 l l l l notification l 7/24/81 l l l l 1 1 I 1 7/9/81 1 Emergency Plan l LL2-81-0186 l l 1 I Information 1 7/30/81 l l l l 1 I I I I I I I I I I I i 1 I i i l I i i l i I i i l I I I I I I I I I I I I l I l l l l l l 1 I l' I i i i l i I I I [1) No Response Required column is used to identify 'mse letters where the NRC did not request a written response to the particular generic letter. Examples of such letters are notifications of meetings, I & E Bulletins for BWRs and transmittal of generic information.
Page 1 of 14 Table 2 Items MRC identified as apoarently not applicable to TMI - 2 l l l D4I-l docket l No (1)! GPU (2)l l Abbreviated l TMI-2 applicable I applicable l Response I Concurs I i Subject l Correspondence ! Correspondence I Required IItems N/A l Comments I I I I l 5/15/79 l Westingtouse NSSS l 1 l X l X l i I I I I I 5/15/79 I PWRs Cracking in I 1 l l X l l Feedwater Lines l l l l l 1 1 I I I I 5/21/79 l I&E Bulletin 79-06l TLL-247 l I X l X l l & 79-06A Responsesi 5/29/80 l l l l l I I I I I 6/11/79 l NUREG-0560 " Staff l 1 l X l X l l Report on the l l i l l I Generic Assessmentl l l I I l of Feedwater l I l l l l Transients in PWR I I I l l l Designed by the l l l l l l B&W Company l l l l l 1 1 I I I I 6/11/79 l Request for Addi-I 1 l X l X l I tional Information! l l l l l Regarding WestJng-l l l l l l house Small Break l l l l l l LOCA Analysis l I l l l 1 I I I I I 6/20/79 l I&E Bulletin 79-081 1 l X l X l -- ---== =- ! Responses l I l l l 1 I I I I I 6/26/79 l Multiple equipmenti See 9/21/79 l I l I l failures in safetyl letter i l l I I related systems I i l l I l for PWRs l I l l l l 1 I I I I 7/13/79 1 Information for 1 1
l X
l X l l NRC Staff Generic l l l l l l Report en BWRs l I I l l l l l l l l 7/16/79 l Operability Test-l
I l
X l X l ---=== - l ing of Relief and l l l l l l Safety Relief I l l l l l Valves for BWRs l l l l l l l l l l l
Page 2 of 14 Yable 2 Items NRC identified as apoarently not aoolicable to TMI - 2 I l l TMI-1 docket l No (1)i GPU (2)l l Abbreviated l TMI-2 applicable l Epplicable l Response l Concurs l l Subject Correroondence l Correspondence l Required Items N/A l Comments i I I 7 /18/79 l NUREG-0473, Rev. 21 l I X l X I" Draft Radiologicall l l l l l Effluent Technicall l l l l l Specifications forl l l l l l BWRs l l l l l l l l l l l 7 /18/79 l NUREG-0472, Rev. 21 l TSCR 34A l
l X
l License Amendnent 16 inplemented [" Draft Raciologicall l l l l PEIS Appendix R Radiological Eny-l Effluent Technicall l l l l ironmental Tecinical Specifications l Specifications forl l l l l l PWRs l l l l l 1 l l l l 7/23/79 l NUREG-0578 "TMI-2 l 1 l X l X l l Lessons Learned" l l l l l 1 l l l l l 8/22/79 l BWR off-gas l I l X l X l l systems enclosing l l l l l f l NUREG/CR-0727 l l l l l l l l l l l l 9/13/79 1 Foli UJp Actions I l l l I See NUREG 0737 item dated 10/31/80 l Rest.1ung frca thel l l l l { j NRC Staff Reviews l l l l l l l Regarding the l l l l l l l TMI-2 Accident l l l l l I I l l l l 1 9/17/79 l Potential Un-l l 1 l X l Environmental Qualifications & l reviewed Question l l l l l high energy line breaks are long I on Interaction l l l l l term items. l Between Non-Safetyl l l l l l l Grade Systems and l l l 1 l l Safety Grade l l l l l l l Systems l l l l l ~ l l l l l l 9/18/79 l Reactor Cavity l l l l l Awaiting receipt of letter. l Seal Ring Generic l l l l l l Issue (PWR) I l l l l I I l l l l l l l l l l i i I l l l j
Page 3 of 14 Table 2 Items NRC identified as apparently not applicable to TMI - 2 l l l TMI-l docket l No (1)l GPU (2)l l Abbreviated l TMI-2 applicable l applicable l Response l Concurs l l Subject i Correspondence l Correspondence Required l Items N/A l Comments i 1 1 I l 9/21/79 l Referencing l l l l X l NRC letter is re-transmittal of l 6/26R9 letter re l l l l . l 6/26/79 letter. I multiple equipmentl l l l l l failures l l l l l l l 1 l l l 9/27/79 l Containment 1 l l l X l l Purging and Vent-l l l l l l Ing During Normal l l l l l l Operations-Guide-l l l l l I lines for Valve l l l l l l Operability l l l l l l l l l l l 10/2/79 i BWRs Mark I l l l X l X l l Containment l l l l l l l 1 l l 1 10/5/79 l Summary of l - -- l l X l X l Environmental Qualifications Long l Meetings held on l l l l l Term item. l 9/18-20n9 to l I l l l l Discuss a Poten-l l l l l l tial Unreviewed l l l l l l Safetv Question onl l l l l l Interaction l l l l l l Between Non-Safety l l l l l l Grade Systems and l l l l l i l NSSS Supplied l l l l l i l Safety Grade i l l l l l Systems (I&E In-l l l l l t l formation Notice l l l l l 2 i l 79-22 l l l l l l l l l l l
- 10/17n9 l ATWS I
l l l X l I I I I l l 10/22n9 l Containment Purge l l l l X l l and Venting Duringl l l l l I Normal Operation l l l l l l l l l 1 i
- fo/13n9 l Summary of Meeting l l
I X l X l l Held on 10/12n9, l l l l l I I to Discuss l l l l l i l l l l l i
~ - Page 4 of 14 Table 2 Items NRC identified as apparently not applicable to TMI - 2 I l l l TMI-l docket i No (1)l GPU (2)l Abbreviated l TMI-2 applicable l applicable l Response l Concurs l l Subject l Correspondence l Correspondence l Required Items N/A l Comments l I l l (con't) l Responses to IE l (see previous l l l l l Bulletin 79-05C l page) l l l l l & High Pressure l l l l l l Injection (HPI) l l l l l l Termination l l l l l l Criteria l l l l l l l l l l l 10/30/79 l Discussion of l l l l X l l l Lessons Learned l l l l l l Short Term - l l l i l i Requirements l l l l l 4 l l 1 l l l l 10/31/79 l Mark I Containment! l l X l X l l BWR l l l l l l I I l l l t 11/9/79 l ECCS calenlations ! l X l l l l { l on fuel cladding l l l l l l l l l l l 11/27/79 l Additional 1 l l l X l l l Information re l l l l l 1 l 11/9/79 letter l l l l l i I I I I I I i 12/17/79 l Audit of Small l 1 l l X l l Break LOCA I l l 1 l I Guidelines l l l l l 1 l l l l l i j 12/20/79 l Cladding Rupture, 1 l I X l X l l Swelling and Cool-l l l l l j l ant Blockage as a l l l l l l l Result of a l l l l l l l Reactor Accident l l l l l i l l l l l l 1/3/80 l NUREG-0630 " Clad-l l l X l. X l .l. I aing, Swelling andl l l l l l Rtpture-Models forl l l l l l l LOCA Analysis" l l l l l l l 1 l l l l l l l l l I I I l l l =,
Page 5 of 14 Table 2 Items t01C identified as apoarently not applicable to TMI - 2 I I l TMI-l docket i No (1)l GPU (2)l I Abbreviated i TMI-2 applicable i @plicable l Response l Concurs l l Subject l Correspondence l Correspondence l Required lItems N/A l Comments I I l l l 1/10/80 i BWR Control Rod 1 l l X l X l l Failures l l l l l 1 I i l l l 1/11/80 l IEB 80-01 Opera-l I l X l X l I bility of ADS I l l l l l Valve Pneumatic l l l l l l Stpply - BWR I l l l l l l l l l l 1/14/80 l IEB-79-OlB l TLL-247 I I l X l Long teIm action item per 1 Environmental l 5/29/80 I l l l referenced correspondence. l Qualifications of l I l l l l Class IE Equipment l l l l l l l l l l l 1/21/80 I IEB 80-02 l TLL-247 I l l X l Referenced correspondence ! Inadequate Qualityl 5/29/80 l l l l indicated item was N. A. 1 Assurance for I l l l l l Nuclear Supplied l l l l l l Equipment l l l l l I I I I I I 2/6/80 l IEB 80-03 Loss of l TLL-247 l I l X l Long term action item per I Charcoal from l 5/29/80 l l l l referenced correspondence-l Standard Type II, I l l l l l 2 Inch, Tray i I I l l l Adsorber Cells l I l l l I I l I I 2/8/80 l IEB 80-04 Analysisl TLL-247 l l --- I X l Long term action item per I of a PWR Main l 5/29/80 l l l l referenced correspondence. I Steam Line Break l l l l l l with Continued l I l l l l Feedwater Additioni l l l l I I I I I I 2/23/80 l LWR Primary l l l l l Awaiting receipt of letter. I Coolant System i l l 1 l l Pressure Isolationl l l l l 1 Valves l l l l l 1 I I I I I I I I I I I I I I I I I I I I I I I
Page _,of _14 Items NRC identified as apparently not applicable to TM1 - 2 I l i TMI-l docket i No (1)! GPU (2) I l Abbreviated l TMI-2 applicable i mplicable l Response l Concurs l I Subject l Correspondence l Correspondence l Required lItems N/A l Comments i I I I I 2/29/80 l IEB 79-018 I TLL-247 l 1 l l Long term action item per i Environmental l 5/29/80 l l l l referenced correspondence. l Qualification of I l l I l l Class IE Equipment l l l l l l l l 1 1 I 3/6/80 l Crystal River 3 i 1 l
l X
l 1 Reactor Trip from i l l I l l Approximately l l l l l l 100% Full Power l l l l l l l 1 I I I 3/10/80 l Enhanced Fission l l l l l Awaiting receipt of letter. I Gas Release l l l l l 1 1 I I I I 3/12/ec I NRC Nuclear Data I 1 i x l x I l Link (NDL) l I l l I I I I I I I 3/13/80 l IEB 80-06 l TLL-335 l 1 l X l Referenced correspondence i Engineered Safety l 7/9/80 l l l l Indicated long term action. I Feature (ESF) I l l l l l Reset Controls l l l l l l l l l 1 1 4/4/80 l IEB 80-07 BWR Jet 1 I I X l X l l Pump Assembly l l l l l 1 Failure l l l l l 1 1 I I I I 4/7/80 l IEB 80-08 I TLL-247 l l l X l Referenced correspondence l Examination of l 5/29/80 l l l l Indicated long term action. I Containment Liner I I l l l l Penetration Welds i l i l l I I I I I I 4/7/30 l Modification to 1 I l X l X l l Boiling Water 1 i l l l l Reactor Control l l l l l l Rod Drive System I l l l l 1 I I I I I 4/17/80 l IEB-80-09 Hydra-l TLL-335 l l l l Response ?nclosed as attachtient 3 l motor Actuator l 7/9/80 l l l l to referenced TLL l Deficiencies l l l l l l 1 l I I I
Page 7 of 14 Table 2 Items NRC identified as apparzntly not applicable to TMI - 2 l I l TMI-1 docket l No (1)i GPU (2)l I Abbreviated l TMI-2 applicable l applicable l Response l Concurs l l Subject l Correspondence i Correspondence l Required litems N/A l Comments I I I I I 4/25/80 1 Clarification of i l l X l l l NRC Requirements l l l l l l for Emergency Re-l l l l l sponse Facilities l l l l l l at Each Site l l l l l l l 1 1 I I 4/25/80 1 Effect of a DC l l l l l Awaiting receipt of letter. 1 Power Supply l l l l l l Failure on ECCS l l l l l l Performance l l i l l I I I I I l 5/6/80 l IEB 80-10 Contam-l TLL-655 l I 1 l l ination of Non-l 12/16/80 l l l l l radioactive System] l l l l l and Resulting l l l l l l Potential for Un-l l l l l l monitored, Uncon-l l l l l l trolled Release l l i l l l to Environment l l l l l l 1 1 I I l 5/8/80 l NUREG-0645 "Reportl l l l I See NUREG 0737 item dated 10/31/80 l of the Bulletins l l l l l 1 and Orders Task I I I I l l Force" and l l l l l l NUREG-0626 I I l l l l" Generic Evaluationl l l l l l of Feedwater Tran-l l l l l l sients and Small l I l l l l Break Loss-of-l l l l l l Coolant Accidents"l l l l l I l l l I I 5/9/80 l IEB 80-12 Decay l TLL-450 1 1 l 1
--- =-
I Heat Removal l 9/22/80 l l l l l System Operabilityl l l l l 1 l l l l l 5 /12 /80 l IEB 80-13 Crackingl l l X l X l l in Core Spray l l l l l l Spargers - BWR I l l l l l l l l l -{>
Page ~3~ of 14 _ Table 2 Items NRC identified as apparently not applicable to TMI - 2 l l l TMI-l docket l No (1)l GPU (2)l I Abbreviated l TMI-2 applicable l @plicable l Response l Concurs l l Subject l Correspondence l Correspondence Required l Items N/A l Comments l l l l 5/19/80 1 Generic Tectnical l l l l l Awaiting receipt of letter. l Activity A-12 l l l l l 1 Fracture Toughnessl l l l l l 1 I I I I 6/3/80 l Nuclear Safeguards l l l l l Awaiting receipt of letter. I Problems l l l l l l l l l l l l X l X l 6/5/80 l Generic Activity 1 l l A BWR Cracks l l l l l l l l l l l 6/11/80 l Decay Heat Removall See Comments 1 1 l l TMI-2 technical specifications l Capability i I l l l address decay heat removal systems = l l l l 1 1 1 6/22 /8 0 l IEB 80-14 l I l X l X l l Degradation of I l l l l l Scram Discharge l l l l l I Volume Capability l l l l l 1 l l 1 I l l l X l Long term action item per 6/27/80 l IEB 80-16 Poten-l TLL-370 l l tial Misapplica-I 7/29/80 l l l l referenced correspondence. I tion of Rosemount l l l l l l Inc., Models 1151 l l l l l l & 1152 Pressure l l l l l l Transmitters with l I l l l l Either "A" or "D" l l l l l l Output Codes. l I l l l l 1 I I I I 6/30/80 l Meetings on EQ l TLL-247 5/29/81 1 l X l l I l l l l l 7/2/80 1 TMI-2 Lessons I l l X l Recovery Technical Specifications l Leamed Model l l l l l reflect status of TMI-2 facilities. l TectTiical l l l l l See also NUREG-0737 dated 10/31/80 l Specifications fori l l l l I NUREG-0578 l l l l 1 i I l l l l 1 7/2/80 l Model Tectnical l l 1 X l X l l I Specifications forl l l l l l NUREG-0578 BWR l l l l l i I l l l l 1 i
Page 9 of 14 Table 2 Items NRC idzntified as apparently not applicault; to TMI - 2 I I I TM1-1 docket i No (1)l GPU (2)l l Abbreviated l TMI-2 applicable l Epplicable l Response l Concurs l l Subject l Correspondence l Correspondence Required lItems N/A l Comment.s i l l l l 7/3/80 l IEB 80-17 Failure I l I X l X l l of Control Rods tol l l l l l Insert During a l l l l 1 l Scram at a BWR l l l l l l l l l l l 7/7/80 l Scram Discharge l l l X l X l l Volume Designs l l l l l l l l l l l l 7/11/80 i Licensing Schedulel l I I l i I l-1 I I I 7/18/80 l IEB 80-17 Supple-l 1 l X l X l r i ment 1 Failure ofl l l l 1 l Control Rods to l l l l l l Insert During a l l l l l l Scram at a MR l l l l l l l l l l 1 7/22/80 l Scram Discharge l l l X l X l l Volume l l l l l l l 1 l l l 7/22/80 l IEB 80-17 Supple-l l l X l X l I ment 2 Failures l l l l l l Revealed by Test-l l l l l l ing Subsequent to l l l l l l Failure of ContIoll l l l l l Rods to Insert l l l l l 1 During a Scram l l l l l l at a BWR l l l l l l l l l l 1 7/24/80 l IEB 80-18 Mainten-l TLL-499 l 1 1 l Long term action item. I ance of Adequate l 10/7/80 l l l l l Minimum Flow Thru l l l l l l Centrifugal Charg-l l l l l l ing Punps Follow-l l l l l l ing Secondary Sidel l l l l l High Energy Line 1 l l l l l Rupture l l l l l l l l l l l l l l 1 I l l l l l l l
Page 10 of 14 l Tabla 2 l Items NRC identified as apparently not applicable to TMI - 2 ~ l l l TMI-l docket l No (1)l GPU (2)l l Abbreviated l T'".-2 applicable l Epplicable l Response l Concurs l l Subject Correspondence l Correspcndence l Required IItems N/A l Comments I i i l l l 7/31/80 l IEB 80-19 Failures l TLL-426 l l l I of Mercury-Wetted i 8/29/80 l l l l [ l Matrix Relays in l l l l l i l keactor Protect-l l l l l [ l ive Systems of I l l l l l l Operating tjuclear l l l l l l l l Power Plants De-l l l l l I l signed by Combust-l l l l l ] l lon Engineering l l l l l i l l l l l l j 8/7/80 l Lessons Leamed 1 l 1 X l l Letter withdrew 7/2/80 tRC letter. : J l Tech Specs, I l l l l l l Amendment Fee l l l l l j l Classification l l l l l i I l l l l l ) i 8/15/80 l Refueling Water l l l l l Awaiting receipt of letter. j l Level l l l l l J l l l-l l 1 j 8/20/80 l Mark I Containmeril l l X l X l i l 1 I I I I r ] 8/22/80 l IEB 80-17 Stpple-l l l X l X l l 1 l ment 3 Failures l-l l l l L j l Revealed by Test-l l l l l l l ing Subsequent to ! l l l l j l Failure of Controll l l l l 4 l Rods to Insert l l l l l j i During a Scram at l l l l l i l a BWR l l l l l t i I l l l l l l 9/5/80 l Preliminary Clar-l
- l l
l l See NUREG 0737 item dated 10/31/C0' l ification of TMI l l l l l l Action Plan l l l l I i l Requirements l l l l l l l l l l 1 i 9/19/80 ! Preliminary 1 l 1 l l See NUREG 0737 item dated 10/31/80, l Clarification l l l l l l j, l TMI Action Plan l l l l l { l Requirements, .1 l l l l j. l. l l l l l l 1 4
Page 11 of 14 Table 2 Ite"ts fGC identified as apparently not aoplicable to IMI - 2 1 l l TMI-l dccket l No (1)] GPU (2) l l Abbreviated l TMI-2 applicable i mplicable l Response l Concurs l l Subject i Correspondence l Correspondence l Required IItems N/A l Comments I I I I I (con't) l Appendum to 9/5 l l l l l l Letter l l l l l I I i i I I 9/30/80 l IEB 79-01B Supple-l TLL-247 I I 1 I Referenced correspondence ' ment 2 Environ-1 5/29/80 l l l l Indicated long tem action item. I mental Qualifica-1 I l l l l tion of Class IE I I l l l l Equipment l I l l l l l l l 1 I /1/80 i EnviIunmental l TLL-247 l l l I Referenced correspondeTe ! Qualification of l 5/29/80 I I l l indicated long te;m action item. I Safety-Related l l l l l l Equipment l l l l l 1 I I I l 10/1/6C l BWR Scram System l I l X l X l l l l l l l 10/6/80 l Safety Issue A-12 1 I l l X l I" Potential for Low l l l l l l Fracture Toughnessl l l l l l and Lamellar Tear-l l I I I l ing on Component i l l l l l Supports" l l l l l l l I I I I 10/21/80 l Seismic Qualifica-l I l I X l I tion of Auxiliary l l l l l l Feedwater Systems l l l l l l l l l l l 10/24/80 I IEB 79-ole Supple-l TLL-247 l I
l l Referenced correspondence I ment 3 Environ-l 5/29/80 l
l l l indicated long tem action item. I mental Qualifica-i l l l l l tion of IE Equip. ! l l l l I l 1 1 10/31/80 I Post TMI Require-I See Table 3 l 1
l l Potentially applicabl? items are:
I ments NUREG-0737 I l l l l I. A.1.2 ; I.C.2 ; I.C.3 ; _.C.4 ; l l l l l l I.C.5; I.C.6; III. A. l.1; j i l l l l III. A.1.2 ; III. A.2 l l 1 I I I
Page 12_ of 14 Table 2 Items NRC icentified as apparently not applicable to TMI - 2 l I I TMI-l docket i No (1)) GPU (2)l l Abbreviated l TMI-2 applicable I mplicable l Response l Concurs l l Subject l Correspondence l Corresoondence l Required IItems N/A l Comments 1 I I I I i 11/4/80 l ODYN Code I I l X 1 X l l Calcula+. ion l i l l l l l l l l l 11/13/80 l Generic Activity 1 l l X l X l l A BWR l l l l l l l 1 l I I 11/20/30 l IEB 80-24 Prevent-l 1 1 l l Response under preparation. I tion cf Damage Duel l l l l l to Water Leakage l l i i l l Inside Containmentl l l l l l l l l l l 11/26/80 l Orders on Environ-l TLL-247 l I l 1 Reference correspondence I mental Qualifica-1 5/29/80 l l l l indicated long term item in I tion of Safety Re-l l l l l accordance with IEB 79-018. I lated Electrical l l l l l l Equipment l I l l l 1 I i i I I 12 /9/8 0 I BWR Scram Dis-l I I X l X l I charge System l l l l l l 1 I I I i 12 /18/80 1 IEB 80-17 Supple-l -- l l X l X l l ment 4 Failure ofl l l l l l Control Rods to l l l l l l Insert During a l l l l l l Scram at a BWR I I I I I I I l l 1 1 12/19/80 l IEB 80-25 Operat-l I I X l X l l ing Problems with l l l l l l Target Rock Safetyl l l l i l Relief Valves l l l l l 1 I I I I I 12/22/80 1 Control of Heavy 1 I I l I Response under preparation. I Loads (Sent to l I I l l l TMI-2 on 2/27/81, I l l l l l letter to Hovey l l l l l l from Snyder. ) l l l l l I I l l 1 l 1 I I I I l I I I l l l
Page 13 of 14 Table 2 Items NRC identified as apparently not applicable to TMI - 2 i j i IMI-l docket l No (1)l GPU (2)l 1 Abbreviated l TMI-2 applicable l applicable l Response l Concurs l l Subject l Correspondence ! Correspondence l Required l Items N/A Comments i I l l l 1/19/81 l Information Re-l TLL-247 l l
l l Referenced correspondence I garding the Pro-l 5/29/80 l
i i l indicated long term action item in i gram for Environ- ! l l l l accordance with IEB 79-018. I mental Qualifica-1 I l l l l tion of Safety-i l I l l l Related Electrical! l l l l l Equipment i I l l l l 1 l l l 1 1/23/81 l BWR Scram Dis-I l X l X l I charge System i l l l l 1 1 I I i 1/29/81 1 ODYN Code I
1 l
X X l l I i l l I 2/3/81 l Control of Heavy 1 l 1 l l Response under preparation. I Loads (Sent to l l l l l l TMI-2 on 2/27/81 l l l l l l letter to Hovey l l l l l l from Snyder. ) l l l l l l l l l l l 2 /10/81 l Seismic Qualifica-l 1 l l X l l tions for Aux-l l l l l l iliary Feedwater l l l l l l Systems l I l l l c I I I I i 2/20/81 l BWR Feedwater I l l X l X l l Nozzle and Controll l l l l l Rod Drive Return l I l l 1 l Line Nozzle Crack-l l l l l l Ing (NUREG-0619) l l l l l l l l l l l 2/26/81 1 Inplementation of l l I X l X l NUREG-0313 on i l l l l 1 Material Selectioni l l l l 1 & Processing l l l l l l Guidelines for BWRI l l l l I I I I I I I I I I I i I I i l i 1 1 I I I I I
Page _ 14 of 14 Table 2 Items tGC identified as apparentlLnot aoolicable to TMI - 2 I I I mI-l docket l No (1)l GPU (2)l 1 Abbreviated i TMI-2 applicable I @plicable l Response l Concurs l l Subject l Correspondence l Correspondence l Recuired lItems N/A l Comments I I I I I 3/10/81 l Environmental l TLL-247 l l l X l Referenced correspondence l Qualification of l 5/29/80 l l l l Indicateo long term action item in l Class IE Electric-l l l l l accordance with IEB 79-018. I al Equipment i l l l l 1 1 I i 1 1 3/30/81 l BWR Scram l l I X 1 X l l Discharge System; I I l l l l Clarification of I I I l l l Diverse l l l l l l Instrumentation l l l l l Requirement l l l l l 1 l 1 1 l l 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i. I I I I i i i l l I I I I I I I I I I I I l l l 1 l l I I I I I I I I I I I I I i 1 I I I I I I I I I I I I I I I i i l l l i 11) No Response Required column is used to identify those letters where the NRC did not request a written msponse to the particular generic letter. Examples of such letters are notifications of meetings, I & E Bulletins for BWRs and transmittal of generic information. 12) GPU Concurs Item is Not Applicable states the GPU position, in concurrence with the NRC, that the generic letter is not aoplicable to TMI-2 in non-power operation modes.
Page 1 of 2 Table 3 I I Date I Abbreviated Subject l Status I i 8/8/79 l Adequacy of Station Electric Distribution System Voltages i Uncer evaluation. I l 9/25/79 I Transmittal of Reports Regarding Foreign Reactor l Awaiting receipt of letter. 1 Operating Experiences l 1 1 1C/17/79 Radioactive Release at North Anna Unit 1 and Lessons l Uncer evaluation. I Learned l I I 1/7/80 l Quality Assurance Requirements Regarding Diesel Generator i Uncer evaluation. I Fuel Oil l l I 5/8/80 l IEB 80-11 Masonry Wall Design l Response uncer preparation. I I 11/24/80 l Appendix R to 10 CFR 50 re. Fire Protection l Response under preparation. I l 11/25/80 l Containment Structures Inservice Inspection Program l Awaiting receipt of letter. I I 2/20/81 1 Fire Protection Rule l Response under preparation. I I 2/25/81 l Emergency Procedures and Training for Station Blackout l l Events l 1 l 9/18/79 i Reactor Cavity Seal Ring Generic Issue (PWR) l Awaiting receipt of letter. l l 2/23/80 l LWR Primary Coolant System Pressure Isolation Valves l Awaiting receipt of letter. I I 3/10/80 l Enhanced Fission Gas Release l Awaiting receipt of letter. 1 I 4/25/80 l Effect of a DC Power Supply Failure on ECCS Performance I Awaiting receipt of letter. I I 5/19/80 l Generic Technical Activity A-12 Fracture Toughness l Awaiting receipt of letter. I I 6/3/80 l tbclear Safeguards Problems l Awaiting receipt of letter. I l 8/15/80 l Refueling hater Level l Awaiting recelot of letter. I I 10/31/80 1 Post TMI Requirements NUREG-0737 l Potentially applicable items are: 1 I I.A.l.2; I.C.2; I.C.3; I.C.4; I.C.5; I.C.6; I I III.A.l.1; III.A.l.2; IIl.A.2 I I
Page 2 of 2 Table 3 l l Date l Abbreviated Subject l Status l I 11/20/80 l IEB 80-24 Prevention of Damage Due to Water Leakage l Response under preparation. l Inside Containment i l i 12/22/80 l Control of Heavy Loads (Sent to TMI-2 on 2/27/81 letter l Response unoer preparation. l to Hovey from Snyder) l I I 2/3/81 l Control of Heavy Loads (Sent to TMI-2 on 2/27/81 letter i Response under preparation. I to Hovey from Snyder) l I I I I I I I I I I I I I I I I I I I I I I I I I i i I i l i I I I I I I I I I I I i l l I I I I I I I i l I I I I I I I I I I}}