ML20195E455
| ML20195E455 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/02/1986 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Thoma J Office of Nuclear Reactor Regulation |
| References | |
| 5211-86-2098, NUDOCS 8606090083 | |
| Download: ML20195E455 (3) | |
Text
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GPU Nuclear Corporation p
Nuclear
=, ors:r8o Middletown, Pennsylvania 17057-0191 717 944-7621 TELEX 84 2386 Writer's Direct Dial Number:
June 2, 1986 5211-86-2098 Office of Nuclear Reactor Regulation Attn:
Mr. John O. Thoma, Project Manager PWR Projects Directorate No. 6 Division of PWR Licensing-B U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Thoma:
Three Mile Island Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Implementation of Generic Requirements On May 13, 1986 TMI-l received your letter dated May 2, 1986 which requested a status of various Multi-Plant Actions (MPA). Since receipt of the letter we have had discussions with you and have obtained additional clarification of your request.
Your letter states that you "do not expect or want a major effort made to obtain precise dates." We believe that you have substantially under-estimated the effort necessary to respond to your request, even though precise dates are not required. The effort needed to properly respond to your request will include:
1.
A thorough search of licensing correspondence which docucents the scope of each item.
2.
A search of the licensees files which would document the actions taken to implement each line item contained in the licensing correspondence.
3.
A physical veritication that the documented actions described have been g
completed.
NNc
@ f The above tasks represent a substantial effort, possibly several man years, 00 and would require a redirection of available resources.
CD O Until recently the NRC has not identified the MPA number to Licensees when m
gg corresponding to them on these issues. Therefore, it is extremely difficult oa to determine what NRC or Licensee correspondence applies to each item. In 7
addition, while we have been provided with brief descriptions of many MPAs, 4
the descriptions are in many cases too shallow to be useful. Also several of 35 the MPAs lack even summary descriptions.
(D a. a.
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation i
5211-86-2098 June 2, 1986 1
Your letter also requested that we add omitted significant actions to the list. Because we are not fully aware of the list's intended use, we are not able to add additional items.
Based on the above we are unable to respond to your request by May 31, 1986.
we request that you provide us with additional clarification as described on the attached list. The c).arifications should be provided to us informerly in order to expedite completion of this task.
Within 30 days of the receipt of the add'itional clarifications, we will provide you with a schedule for responding to your request and a more accurate estimate of the effort necessary to fulfill it.
Sincerely, H.D.}
till Vice President and Director, TMI-l HDH/CWS/spb I
cc:
T. Murley J. Stolz R. Conte 0598A i
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MULTI-PLANT ACTION STATUS REOUEST FOR CLARIFICATION 1.
Please provide a description of the scope of each MPA if not already provided.
2.
Please provide a letter date for the NRC safety evaluation for each MPA.
If the SER has not been formally provided to GPUN please also include a copy of the SER.
3.
Please provide dates and/or-letter numbers for letters that the NRC believes are relevant to each MPA.
, m -.
y f,Je %gJg UNITED STATES NUCLEAR REGULATORY COMMISSION 3
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WASHINGTON, D. C. 20555 I
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$2tI-g(c 5tl4 QSJ Docket No. 50-289 Mr. Henry D. Hukill, Vice President and Director - TMI-1 GPU Nuclear Corporation P. O. Box 480 Middletown, Pennsylvania 17057
Dear Mr. Hukill:
The Comptroller General in a Report to the Congress dated September 19, 1984, stated "NRC needs better management controls to ensure implementation of generic issue solutions." To correct this situation, the Nuclear Regulatory Commission is working on a long-term program which will improve its documentation on the status of power reactcr licensees' implementation of approved regulatory improvements.
To assist me in developing this information for Three Mile Island, Unit No.1, please review the enclosed plant-specific list, add omitted significant actions to the list, and provide the date that all aspects of each identified reoui.rement were completed / implemented 6r are expected to be completed.
For each requirement that has been completed, enter " completed" under tne Status column and the date the item was completed.
For requirements that have not been completed / implemented, provide the projected date and enter !' projected" under the Status column.
I do not expect or want a major effort made to obtain precise dates. Rather, I will accept readily-known or best-estinate dates for actions that have been completely implemented.
For example, the year only would be acceptable for completions prior to 1984; the month as well as year is needed for requirements completed af ter that tine.
For projected completions / implementations in 1986, use month and year. Use year only for projections thereafter.
Please provide a response in.the form of a marked up listing by May 31, 1986.
In the future, NPP will need estimated dates prior to issuance of the safety evaluation so that the estinated schedule may be included in the evaluation.
This request is covered by OMB Clearance Number 3150-0011, which expires September 30, 1986.
Sincerely, M.
I sohn Thona, Project Manager PWR Project Directorate 76 Division of PWP Licensing-B
Enclosure:
As stated cc w/ enclosure: See next page J6ef!605!1'
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a Q-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.'s 4
FACIL ITY IMPLEMENTATION 03/31/
FACILITY: THREE MILE ISLAND 1 PLANT LOCATION: 10 MI SE OF NARRISBURG, PA LICENSED POWER: 2535 MHT PROJECT MANAGER:
J.
THOMA DOCKET NUMBER: 050-00289 DESIGN PONER:
0819 MHE BRANCH CHIEF:
J.
STOLZ A*JCN/ ENGINEER: GIL NSSS VENDOR:
B&W LIC. ASSISTANT:
R. INGRAM IE INSPECTOR:
R. CONTE LIC ACT LICENSEE IAC NO.
MEA _1 TITLE COMPLETE STATUS g&Ig l
M07057 A-01 to CFR 50.55 A(G) - ISI 05/07/80C M08156 A-02 APPENDIX I - ALARA1 08/06/81C M07489 A-03 SECURITY REVIENS-MODIFIED AMENDMENT PLANS 02/23/79C M08710 A-04 APPENDIX J - CONTAINMENT LEAK TESTING 03/30/81C M11376 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 01/22/81C 0
M10562 A-10 CONTINGENCY PLANNING 04/22/81C M10568 A-11 GUARD TRAINING PLANS
^
04/22/81C M10565 A-12 VITAL AREA ANALYSIS
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03/01/82C M11287 A-14 luCFR 50.55 A(G) - INSERVICE TESTING 08/03/81C M12560 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 04/11/80C M47086 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 04/12/82C M51361 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 12/30/86
,- M55750 A-18, T,ECH SPECS AFFECTED BY 50.72'AND 50.73 (GL 83-43).
04/30/36 M59151 k-20 10-CFR 50.62 OPERATING REACTOR REVIENS 12/31/88 2
)
M55990 A-21 10 CFR 50.61, PRESSURIZED THERMAL SHOCK RULE 04/30/86
-09/19/78C M06466 B-02 FIRE PROTECTION
'M08403 B-03 PHR MODERATOR DILUTION 1
- 02/01/80C 4
06/15/80C M06708 B-04 REACTOR VESSEL OVERPRESSU,RE PROTECTION M08172 B- 08 PHR NPSI-LPSI FLDH RESISTANCE 09/02/80C M08707 S-12 STEAM GENERATOR TUBE INSPECTION 12/22/78C I
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R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.
i FACILITY IMPLEMENTATION 03/31e THREE MILE ISLANC 1 (CONTINUATION) i LIC ACT LICENSEE TAC NO.
MPA 0 TITLE COMPLETE STATUS R&IE i
M19850 B-14 CEA GUIDE TUBE HEAR 07/24/81C M12147 B-16 EMERGENCY PLANNING AND REVISIONS 01/26/81C M11286 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 09/30/84C M07006 B-18 HORTHINGTON RHR PUMP SHAFT INTEGRITY 03/21/79C 4
M10322 3-20
. CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 08/25/80C M10380 3-21 LOSS OF 125-V DC BUS VOLTAGE WITH LOSS OF ANNUNCIA 02/28/82C M08604 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 01/01/70C 3
M10055 3-23 DEGRADED GRID VOLTAGE 01/01/70C M10969 B-23 DEGRADED GRID VOLTAGE 07/29/81C M10205 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 08/25/80C l
M42602 3-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL POW 03/25/85C M19259 B-26 INADVERTANT SAFETY INJECTICN DURING COOLDOHN 09/14/79C 4
M19533 B-35 ORIFICE ROD ASSEMBLY INTEGRITY - B&W 02/01/80C
]
N08608 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 10/26/79C M11234 B-41 FIRE PROTECTION - FINAL TECH SPFCS (INCLUDES SER S 05/15/84C M11742 B-42 TMI FOLLON UP - ALL PLANIS 04/01/80C M12879 B-45 NASH 1400 EVENT V,
" PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C M12301 3-46 ANALYSIS OF TUR8INE DISC CRACKS 11/03/81C M12737 B-47 ECCS; CLAD SHELLING AND RUPTURE 04/24/81C
- M8386 B-48 ADEGUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 05/13/82C P
M42127 B-57 DHR CAPABILITY 03/30/86 M42919 B-59 MASONRY HALL DESIGN 08/08/83C M42513 B-60 ENVIRONMENTAL QUALIFICATION 04/23/85C
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R-1208731-001 REGULAT0RY INF0RMA7 ION TRACKING SYSTEM
,PAGE NO.'s FACILITY IMPLEMENTATION 03/31<
THREE MILE ISLAND 1 (CONTINUATION)
LIC ACT LICENSEE TAC No.
MPA 0 TITLE COMPLETE STATUS R&lE M42710 B-61 LOSS OF NON CLASS IE ISC POWER 07/28/42C M42781 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 11/18/LIC M43921 5-63 INTERIM PROCEDURES FOR SNORT TERM BLACKOUT 11/10/810 i
M43262 B-64 BSC INDUCED FLUX ERRORS 04/30/82C M47157 B-66 NATURAL CIRCULATION COOLDOHN 06/05/84C M47551 3-67 THERMAL SNOCK 02/03/53C M47026 B-67 THERMAL SNOCK 01/15/82C M46864 B-69 IES 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 07/21/82C M46638 B-70 FATIGUE TRANSIENT LIMIT TS 05/25/82C 4
M59764 B-72 NUREG 0737 TECN SPECS (GENERIC LETTER 82-16) 05/10/84C j
M49615 B-73 PLANS FOR PREVENTING EXCEEDING PTS SCREENING CRITE 12/27/83C M52808 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION 8 05/31/85C M52889 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION 8 VENDOR INTER 11/30/86 M52970 B-78 ITEMS 3.1.1 8 3.1.2 -POST MAINTENANCE TEST PROCEDU 10/28/85C M53051 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 10/1E/85C M53105 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 10/28/85C M53158 B-81 ITEMS 4.2.1 8 4.2.2 -PREVENTATIVE MAINT PROG FOR R 12/12/85C M53200 B-82 ITEM 4.5 - AUTOMATIC ACTUATION OF SNUNT TRIP ATTAC 07/12/84C M53641 B-85 SALEM ATHS 1.2 DATA CAPABILITY 03/30/86
- M53724 B-86 SALEM ATHS 2.2 S-R COMPONENTS 12/30/87
}
M53807 B-87 SALEM ATHS 3.2.1 8 3.2.2 S-R COMPONENTS 10/28/85C M53890 5-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 08/02/85C 4
M53945 B-89 SALEM ATHS 4.2.5 8 4.2.4 LIFE COMPONENTS 10/30/86 j
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4-FACIL ITY IMPLEMENTATION 03/31/;
THREE MILE ISLAND 1 (CONTINUATION)
LIC ACT LICENSEE TAC No.
MPA 8 TITLE COMPLETE STATUS R&lg M55382 B-90 ' SALEM ATHS 4.3 H AND 88H T.S.
09/15/84C M53959 B-91 SALEM ATHS 4.4 B8W TEST PROCEDURES 04/30/86 M54117 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 10/28/85C M54034 B-93 SALEM ATHS 4.5.2 & 4.5'.3 TEST ALTERNATIVES 04/30/57 M06371 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 02/20/80C M08709 C-03 QUALIFICATIONS OF RADIATION PROTECTION MANAGER 04/30/80C M08613 C-04 FILTER TECH SPECS 06/05/80C M08708 C-05 CONVERSION TO STANDARD TECH SPECS 01/20/82C M08590 C-06 PUMP SUPPORT-LAMELLAR TEARING 12/12/79C M08515 C-07 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 12/31/79C M08086 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASEI) 12/01/81C M47131 C-10 CONTROL OF HEAVY LOADS OVER SPENT FUEL POOL (PHASE D) 01/11/85C M43654 C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 08/11/83C M52279 C-15 CONTROL OF HEAVY LOADS - PHASE II (FDL LOHUP OF MPA 06/28/85C M58096 C-16 UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERN 01/08/86C M06103 D-08 DEFICIENCY IN CHEM ADDITION TO CONTAINMENT SPRAYS 04/02/80C i
M08603 D-10 ASYMMETRIC LOCA LOADS 03/27/84C 1
M10109 D-11 FISSION GAS RELEASE 05/16/80C M08012 D-13 58W SMALL BREAK ERROR 03/16/79C "M08601 0-14 REACTOR VESSEL HELD - HIRE DEFICIENCY 10/26/79C M12327 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 01/01/70C M43043 D-17 DEFINITION OF OPERABLE 08/07/84C M51733 D-18 NUREG 0630 CLADDING MODELS (B&H PLANTS) 10/28/83C
R-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.*
4 FACILITY IMPLEMENTATION 03/31/
THREE MILE ISLAND 1 (CONTINUATION)
LIC ACT LICENSEE TAC No.
MPA 8 TITLE COMPLETE STATUS DATE M55912 D-19 DIESEL GENERATOR RELIABILITY TECM SPECS (GL 84-15) 10/11/85C M06545 E-01 SPENT FUEL POOL EXPANSIONS 12/19/77C M06495 E-02 FUEL CASK DROP 09/15/81C M08611 E-03 CORE RELOADS REQUIRING PRIOR HRC APPROVAL 03/16/79C 1
M48283 F-05 I.C.1.2/3.8 PROCEDURES GENERATION PACKAGES (NUREG 03/28/84C M47257 F-06 I.C.5 FEEDBACK OF OPERATING EXPERIENCE 02/01/82C M47329 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 01/01/82C M51211 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEW PROGRA 04/08/85C M51291 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 12/23/85C M44411 F-10 II.B.1 RCS HIGN POINT VENTS 10/17/83C M47980 F-11 1I.8.2 PLANT SHIELDING 03/28/83C 4
M48284 F-12 II.B.3 POST ACCIDENT SAMPLING 03/22/84C M44624 F-14 II.D.1 RV AND SV TRAINING 08/22e84C M44710 F-16 II.E.1.2.1 AFH SYSTEM INITIATION 09/27/82C M44756 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATION 04/02/81C M47641 F-23 II.F.1.4 CONTAINMENT PRESSURE INSTRUMENT 04/20/84C M47712 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 04/20/84C M47783 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 04/20/84C M47048 F-26 II.'F. 2 INSTRUMENTS FOR DETECTION ON INADEQUATE 01/31/87
- M48285 F-27 II.K.2.9 FMEA ON ICS 98/02/82C M54979 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/05/84C M45210 F-31 II.K.2.14 LIFT FREQUENCY OF PORVS AND SVS 04/22/81C M45274 F-36 II.K.3.1 AUTO PORV ISOLATION 05/05/84C
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FACILITY IMPLEMENTATION 03/31/
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LIC ACT LICENSEE TAC NO.
MPA 8 TITLE COMPLETE STATUS Hale M45320 F-37 II.K.3.2 REPORT ON PORV FAILURES 03/05/84C M48?)6 F-39 II.K.3.5 AUTO TRIP OF RCPS 03/10/23C M45671 F-47 II.K.3.17 ECCS OUTAGES 02/24/02C M48285 F-57 II.K.3.30 58 LOCA METHODS 07/12/857 M48208 F-58 II.K.3.31 COMPLIANCE HITN 10 CFR 50.46 03/30/87 M45987 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 09/30/86 M46058 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 09/30/86 M46130 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 09/30/86 M46202 F-66 III.A.1.2 NUCLEAR DATA LINK 12/10/80C M46274 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 03/09/84C M48287 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 09/30/86 M67049 F-70 III.D.3.4 CONTROL ROOM HA8ITA81LITY 08/22/84C M56174 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEH (FOLLOHUP TO 04/08/85C M49698 G-0,1 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 05/28/86 e
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