ML19332F218
| ML19332F218 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/01/1989 |
| From: | Whittier G Maine Yankee |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GDW-89-372, GL-89-21, MN-89-146, NUDOCS 8912140060 | |
| Download: ML19332F218 (9) | |
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S MaineVankee RE LtADLE ELLCTRICpY f OR MAINE 7>l5dfrO~2 EDISON DRIVE
- AUGUSTA, MAINE 04336 * (207) 622 4868 l'
December 1, 1989' L
MN-89-146 GDW-89-372 l
UNITED STATES NUCLEAR REGULATORY COMMISSION
' Attention: Document Control Desk Washington, DC 20555
References:
(a)
License N0. DPR-36 (Docket No. 50-309)
(b)
USNRC Letter dated October 19, 1989, Request for Information Concerning Status of Implementation of 4
Unresolved Safety Issue (USI) Requirements (Generic Letter 89-21)
Subject:
Response to Generic Letter 89-21, Implementation of Unresolved Safety Issue (USI) Requirements Gentlemen:
. Maine Yankee has reviewed the status of--implementation of Unresolved Safety-Issues, as~ requested and identified in Reference (b). Attached is an annotated copy.of Enclosure (1) of Reference (b). We have marked the attachment with our judgement of. status based on a review of our records for each item as applicable
. to Maine Yankee. This status report is.not intended to make any commitments for Maine Yankee or modify any ' previous-commitments.
Al so, please note the attachment provides expected dates of implementation for several pending items.
Maine Yankee considers these dates tentative based on our current plans.
Should you have any questions on the attached, please contact me.
Very truly yours,
$UAdlbf
[vG.D.Whittier, Manager Nuclear Engineering and Licensing RCC':WSD Attachment (Annotated Enclosure (1) of Generic Letter 89-21)
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Mr. William T. Russell Mr. Eric J. Leeds Mr. Cornelius F. Holden GDW89372.LTR g
O 8912140060 891201
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ATTACHMENT
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- Annotated copy of. Enclosure (1) of NRC Generic Letter 89-21
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GDW89372.LTR
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.n ENCLOSURE l'
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-UNRESOLVED SAFETY? ISSUES FOR WHICH A' FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE
-REF. DOCUMENT
' APPLICABILITY STATUS /DATE*
. REMARKS 1
A-1 Water Hammer SECY 84-119-All NUREG-0927, Rev. 1
-C/2 Attached-NUREG-0993, Rev. I NUPEG-0737 Item I.A.P.3 SRP revisions A-2/
Asymmetric Riowdown NUREG-0609 PWR C/1980 Attached MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Coolant Systems A-3 Westinghouse Steam NUREG-0844 W-PWR NA Generator Tube Integrity SECY 86-97 SECY 88-?72 GL 85-02 (No requirements)
A-4 CE Steam Generator Tube NUREG-0844,.SECY 86-97 CE-PWR C/5-88 Attached '
Integrity SECY 88-272 GL 85-02 l
(No requirements)
]
A-5 B&W Steam Generator NUREG-0844, SECY 86-97 R&W-PWR NA Tube Integrity SECY 88-272 GL 85-02
'(No Requirements)
E l-6 Mark I Containment NUREG-0408 Fark I-BWR NA Short-Term Program 4
oC-CHANGES WERE MADE AS A RESULT OF THIS USI AND NO OTHER CHANGES ARE PLANNED..
NC - NO CHANGES 4ERE MADE AS A RESULT OF THIS USI.
NA - NOT APPLICABLE I - CHANGES ARE PLANNED AS A RESULT OF THIS USI.
E - USI UNDER EVALUATION.
1\\1-s USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY-STATUS /DATE*
REMARKS A-7/
Mark I Long-Term NUREG-0661 Mark I-BWR NA D-01 Program NUREG-0661 Suppl. I GL 79-57 A-8 Mark II Containment NUREG-0808 Mark II-BWR NA Pool Dynamic loads NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.1.1C l
GDC 16 A*
Anticipated Transients NUREG-0460, Vol. 4 All I/92 Attached Without Scram 10 CFR 50.62 A-10/
BWR Feedwater Nozzle NUREG-0619 BWR NA MPA B-25 Cracking Letter.from DG Eisenhut dated 11/13/80 GL 81-11~
A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All
.NC Attached Toughness 10 CFR 50.60/
l 82-26 1
A-12 Fracture Toughness of NUREG-0577, Rev. 1 PWP NA Attached Steam Generator and SRP Revision Reactor Coolant Pump 5.3.4 Supports l
A-17 Systems Interactions Ltr: DeYoung to All I
Attached ~
licensees - 9/72 NUREG-1174, NUREG.
1229, NUREG/CR-3922, NUREG/CR-4261, NUPEG/
CR-4470, GL 89-18 f(No requirements)
A-24/
Ocalification of Class NUREG-0588, Rev. 1 All
~ C/6-84 Attached MPA B-60 lE Safety-Related SRP 3.11 Equipment 10 CFR 50.49 GL 82-09. GL 84-24 GL 85-15
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USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*
kEMARKS-A-26/
Reactor Vessel Pressure DOR Letters to PWR C/3 EAttached MPA B-04 Transient Protection
- Licensees 8/76 NUREG-0224 NUREG-0371 SRP 5.2 GL 88-11 A-31 Residual Heat Removal
-NUREG-0606
.All OLs After NA Shutdown Requirements RG I.113, 01/79.
A-36/
Control of Heavy Loads NUREG- 0612 All C/1-85' Attached C-10, Near Spent Fuel SRP.9.1.5 C-15 GL 81-07, GL 83-42, GL 85-11 Letter from DG Eisenhut dated 12/22/80 A-39 Determination of SRV NUREG-0802 BWR NA cool Dynamic Loads NUREGs-0763,0783,0802 and Pressure Transients NUREG-0661 SPP-6.2.1.1.C A-40 Seismic Design SRP-Revisions, NUREG/
All NA
. Attached Criteria CR-4776, NUREG/CR-0054, NUREG/CR-3480, NUREG/
CR-1582, NUREG/CR-1161, NUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509 A-42/
Pipe Cracks in Boiling NUREG-0313, Rev. 1 BWR NA MPA B-05 Water Reactors NUREG-0313 Rev. 2 GL 81-03, GL 88-01
-, =-
- USI/ PPA NUMBER TITLE REF.-DOCUMENT APPLICABILITY STATUS /DATE*
REMARKS ~
A-43 Containment Emergency NUREG-0510, All
.C/12-82
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Attached Sump Performance NUREG-0869, Rev. 1 NUREG-0897, R.G.I.87 (Rev. 0), SRP 6.2.2 GL-85-22 No Requirements A-44 Station Blackout RG 1.155 All C/6-89 Attached MUREG-1032 NUREG-1109 10 CFR 50.63 A-45 Shutdown Decay Heat SECY 88-260 All I/12-91 Attached Removal Requirements NUREG-1289 NUREG/CR-5230
.SECY 88-260 (No requirements)
A-46 Seismic Qua!ification N9 REG-1020 All C/12-88 Attached of Equipment in NUREG-1211/
Operating Plants GL 87-02, GL 87-03 A-47 Safety' Implication NUREG-1217, NUREG-All E/3-90 Attached o# Control Systems 1218 i
GL 89-19 A-48 Hydrogen Control 10 CFR 50.44 All, except NA Measures and Effects SECY 89-172 PWRs with of Hydrogen Burns large dry on Safetv Equipment containments 4
A-49 Pressurized Thermal RGs 1.154, 1.99 PWR NC Attached Shock SECY 82-465 SECY P.3-288 SECY 81-687 10 CFR 50.61/
GL 88,
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Maine Yankee Remarks to Enclosure (1) of NRC Generic Letter 89-21 V11 REMARKS (Correspondence unless otherwise indicated)
A-l' feedwater System:-
NRC-MY, 04/05/83 - Inspection Report No. 50-309/83-01 NRC-MY, 03/18/83 - Inspection Report No. 50-309/83-03 MY-NRC, 02/18/83 (MN-83-31) - LER 83-002/01T-1, Main Feedwater System MY-NRC, 02/17/83 (MN-83-29)
A-2 CEOG-NRC, 11/20/87 (CE0G-87-662)
" Applicability of Leak-Before-Break to the Primary Coolant System Piping of CE-Designed PWRs" MY-NRC, 09/26/84 (MN-84-152) - Information to Support SER NRC-MY, 05/31/84 i
MY-NRC, 07/01/80 (WMY 80-104) j MY-NRC, 05/14/80 (WMY 80-75)
A-4 MY-NRC, 06/23/89-(MN-89-85) - Modify Commitment of.MN-85-135 MY-NRC, 07/12/85 (MU-85-135) - Response to G.L. 85-02 A-9 MY-NRC Due NRC-MY, 08/03/89 - RAI MY-NRC, 05/18/89 (MN-89-63)
A-11 MY-NRC, 12/06/88 (MN-88-ll8)
NRC-MY, 11/20/86 - SER WCAP-9875 A-12 NA. Per Generic Letter 89-21:
"Only applied to plants with a new construction permit issued after October 1983."
L A-17 Remaining action is to complete plant specific PRA l
MY-NRC, 10/31/89 (MN-89-126) - Response to G.L. 88-20, PRA Status NRC-MY, 04/27/81 - Inspection Report No. 50-309/81-06, for TMI Task Action Plan Item I.C.5 A-24 NRC-MY, 10/23/89 - Inspection Report No. 50-309/89-16 NRC-MY, 11/19/87 - Inspection Report No. 50-309/87-16 MY-NRC, 01/25/85 (MN-85-17) - Certification of Compliance to 10 CFR 50.49 MY-NRC, 01/03/85 (MN-85-01) - Update NRC-MY, 12/13/84 - SER MY-NRC, 05/31/84 (MN-84-95) - Response to 04/08/83 SER MY-NRC, 05/20/83 (MN-83-110) - 10 CFR 50.49 Response NRC-MY, 04/08/83 - SER MY-NRC, 09/02/81 (FMY 81-133) - Response NRC-MY, 06/01/81 - SER and Order GDW89372.LTR
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Maine Yankee Remarks to Enclosure (1) of NRC Generic letter 89-21 (continued) 1!11 REMARKS (Correspondence unless otherwise indicated)
A-26 MY-NRC,12/06/88 (MN-88-118) - Update for 10 CFR 50.61 MY-NRC,12/02/88 (MN-88-ll6) - Proposed Change No.145 to Technical Specifications in response to NRC Generic letter 88-11 NRC-MY, 04/06/88 - Inspection Report No. 50-309/88-03, Section ll, Closeout of SlHS item A-26 NRC-MY, 02/27/81 - Technical Specification Amendment No. 53, Incorporated Overpressure Mitigation System (OMS)
MY-NRC, 10/16/79 (WMY 79-117) - Proposed Change No. 72 to Technical Specifications NRC-MY, 09/11/79 - SER on OMS MY-NRC, 02/24/78 (WMY 78-18)
OMS Technical Specifications, for information A-36 Phase I:
NRC-MY,03/21/86-Inspection Report No. 50-309/86-01, Section 3.a NRC-MY, 12/30/83 - SER MY-NRC, 10/06/83 (MN-83-221)
MY-NRC, 05/27/83 (MN-83-115)
NRC-MY, 05/24/83 - R.A.I.
MY-NRC, 05/10/83 (MN-83-94)
MY-NRC, 08/27/82 (MN-82-169)
MY-NRC, 09/18/81 (FMY 81-141)
Phase II:
NRC-MY, 06/28/85 - Generic Letter 85-11 (letter stated that Phase II is considered completed.)
MY-NRC, 03/19/84 (MN-84-22)
Maine Yankee Design Change EDCR 85-32 (0AS 7-5-7) - Single failure proof l-rewiring of AC solenoid brakes on reactor containment, turbine hall, and fuel building / yard cranes, in response to NRC Letter 1
12/19/83 (Generic letter 83-42).
A-40 See A-46 A-43 Maine Yankee Design Change EDCR 82-30 A-44 MY-NRC, 04/14/89 (MN-89-60)
A-45 MY-NRC,10/31/89 (MN-89-126) - Response to Generic letter 88-20, PRA Status GDW89372.LTR l
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I Maine Yankee Remarks to Enclosure (1) of NRC Generic letter 89-21 (continued)
A-46 NRC-MY,.08/31/87 - Audit of Plant Changes... Seismic Upgrades MY-NRC, 06/30/87 (MN-87-67) - Resolution of USI A-46 l
NRC-MY, 03/26/87 - SER - Seismic Margin Program MY-NRC, 02/26/87 (MN-87-22)
MY-NRC, 03/24/86 (MN-86-45)
MY-NRC,'03/14/86 (MN-86-41)
MY-NRC, 10/18/85 (MN-85-181)
NRC-MY,10/29/84 A-47 Response to NRC Generic Letter 89-19, dated 09/20/89, is due 03/19/90 A-49 MY-NRC, 12/06/88 (MN-88-ll8) - Update per SER Request NRC-MY, 11/20/86 - SER - 10 CFR 50.61 MY-NRC, 01/21/86 (MN-86-14) - Response to Requirement of 10 CFR 50.61 (Pressurized Thermal Shock Rule) i l
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GDW89372.LTR
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