ML19332E910
| ML19332E910 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 11/30/1989 |
| From: | Keuter D SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR AGM-NUC-89-256, GL-89-21, NUDOCS 8912130146 | |
| Download: ML19332E910 (5) | |
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SACRAMENTO MUNICIPAL UTILITY DISTR 6CT C 6201 S Street, P.o. Box 15830. Sectamento CA 95852-1830,1916) 452 3211 AN ELECTRIC SYSTEM SERVING THE HEART OF CALIFORNIA j..
L AGM/NUC 89-256 November 30. 1989 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Hashington, DC 20555 Docket No. 50-312 i
Rancho Seco Nuclear Generating Station License No. DPR-E4
. REQUEST FOR INFORMATION CONCERNING STATUS OF IMPLEMENTATION OF UNRESOLVED SAFETY ISSUE (USI) REQUIREMENTS (GENERIC LETTER 89-21)
Attention:
George Knighton Generic Letter 89-21 requested our review and reporting of the status of implementation of Unresolved Safety Issues (USI) for which the final technical resolution has been achieved.
The attached markup of Enclosure 1 of the Generir Letter indicates the status of each USI.
Those items which are incomplete 01under evaluation may be postponed indefinitely due to the status of Ranciso Seco.
Members of your staff with questions requiring additional information or clarification may contact Steve Crunk at (209) 333-2935, extension 4913.
Sincerely, v
Dan R. Keuter Assistant General Manager Nuclear Attachment cc w/atch:
'J. B. Martin, NRC, Halnut Creek A. D' Angelo, NRC, Rancho Seco G. Kalman, NRC, Rockville plfi e
L 8912130146 891130 DR ADOCK 05 g2 gi RANCHO SECO NUCLEAR GENERATING STATloN D 14440 Twin Cities Road, Herald, CA 95638-9799:(209) 333 2935
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ENCLOSURE 1
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UNRESOLVED SAFETY ESSUES FOR WHICH A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED USI/MPA i
fRNMER TITLE REF. 00CtBENT APPLICA8ILITY STATUS /DATE*
REMARKS l
A-1 Water Hammer SECY 84-119 All C/ 12-80 Nattimoe to Eisenhut NUREG-09?7, Rev. I letter dated 12/15/80 NUREG-0993 Rev. I states Item I.A.2.3 is NUREG-0737 Item complete.
i f.A.2.3 SRP revisions l
A-2/
Asynsietric Blowdown NUREG-0609 PWR C/ 2-86 SER of BHOG Reports i
MPA D-10 Loads on Reactor Primary GL 84-04. GDC-4 (2/18/86) stated Coolant Systems I
acceptability of " leak-before-break" approach.
A-3 Westinghouse Steam NUREG-0644 W-PWR N/A Generator Tube Integrity SECY 86-97 SECY 8R-772 GL 85-02 (No requirements)
A-4 CE Steam Generator Tube NUREG-0844. SECY 86-97 CE-PWR N/A Integrity SECY 88-272 GL 85-02 (No requirements)
A-5 R8W Steam Generator NUREG-0844 SECY 86-97 88W-PWP C/ 6-85 Program description Tube Integrity SECY 88-272 submitted via 6/11/85 GL 85-02 Rodriquez to Thompson (No Requirements) letter.
E A-6 Mark I Containment NUREG-0408 Park I-BWR N/A Short-Teria Program
- C - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICA8tE I - INCOMPLETE E - FVALUATING ACTIONS REQUIRED
. USI/WA Nt#SER _.
TITLE REF. DOCtMENT APPLICASILITY STMUS/DATE*
REMRRKS A-7/
Mark I Long-Tern MUREG-0661 N rk I-8WR N/A D-01 Program NUREG-0661 Suppl. I GL 79-57 A-8 h rk II Containment NUREG-0808 Mark II-8WR N/A Pool Dynamic Loads NUREG-0487, Suppl. 1/2 NUREG-0802 SPP 6.2.1.1C GDC 16 I
Hardware changes remain A-9 Anticipated Transients NUREG-0460, Vol. 4 All
- May be postponed Without Scram 10 CFR 50.62 indefinitely due to current plant status A-10/
BWR Feedwater Nozzle NUREG-0619 8WP N/A MPA B-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 0/
4-86 D. Crutchfield to J. H.
A-Il Reactor Vessel Material NUREG-0744, Rev. 1 All Taylor SER dated 4/30/86 Tomohness 10 CFR 50.60/
R2-26 A-12 Fracture Toughness of NUREG-0577, Pev. 1 PWP N/A Applicable to PWR w/CP Steam Generator and SRP Revision later than 10/83 Reactor Coolant Pump 5.3.4 Supports A-17 Systems Interactions Ltr: DeYoung to All E
May be postponed ifcensees - 9/77 indefinitely due to NUREC-1174, Nt9EG-current plant status.
1229, NUREG/CR-3922, NUREG/CR-4761, NUPEG/
CR-4470, GL 89-18 (No requirements)
A-24/
Oualification of Class MIREG-0588, Rev. 1 All C/
11-85 Compliance achieved by PPA B-60 IE Safety-pelated SRP 3.11 10 CFR 50.49 due date of Equipment 10 CFR 50.49 11/30/85 GL 82-09, GL 84-24 GL 85-15
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USI/MPA_
NIMRER TITLE REF. 00CtMENT APPLICA8ILITY STATUS /DATE*
REMARp's A-26/
Reactor Vessel Pressure DOP. Letters to-PWR I
Detailed review of LTOP MPA 8-04 Transient Protection Licensees 8/76 setpoints remains.
NUREG-6224 Postponed indefinitely NUREG-0371 due to current plant SRP 5.2 status.
GL 88-11 A-3!
Residual Heat Reseval MUREG-0606 All OLs After N/A Shutdown Requirements RG 1.113, 01/79.
Control of Heavy Loads NUREC-0612 All C/
6-85 GL 85-11 (6/28/85)
C-10, Near Spent Fuel SRP 9.1.5 closed requirements.
C-15 GL 81 07, GL 83-42, i
GL 85-11 Letter from DG Eisenhut cated t
12/22/80 1
A-39 Determination of SRV NUREG-0802 BWR N/A Pool Dynamic Loads NUREGs-0763,0783,0002 and Pressure Transients NUREG-0661 SPP 6.2.1.1.C I
A-40 Seismic Design SRP Revisions, nyergf gij I
SQUG Monitoring Issue Criteria CR-4776. NUREG/CR-0054, and Necessary Changes NUREG/CR-3480. NUREG/
CR-1582, NUREG/CR-116J.
NURFG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 I
l NUREG/CR-3509 A-42/
Pipe Cracks in Boiifng NUREG-03I3 Rev. I BWR N/A MPA 8-05 Water Reactors NUREG-0313. Rev. 2 GL 81-03, GL 88-01 i
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- USI/ PPA NINSER TITLE REF. DOCUENT APPLICABILITY STATUS /DATE*
REPARKS NUPEG-0510, All C/
3-89 Design review criteria A-43 Containment Emergency' NUREG-0069. Rev. 1 upgraded 3/22/89 Sump. Performance NUREG-0897. R.G.I.87 (Rev. 0), SRP 6.2.2 GL 85-22 No Nequirements A-44 Station Blackout RG 1.155 All I
Hardware, procedure, NUREG-1032 training changes NUREG-1109 required. Postponed 10 CFR 50.63 indefinitely due to current plant status.
A-45 Shutdown Decay Heat SECY 88-260 All N/C IPE Subsumed issue and Removal Requirements NUREG-1289 NUREG/CR-5230 may no longer be SECY 88-260 applicable due to (No requirements) current plant status A-46 Seismic Qualification NUREG-1030 All I
Requirements and Approach under of Equipment in NUREG-1211/
Operating Plants GL 87-02. GL B7-03 development A-47 Safety Implication NUREG-1217, NUREG-All E
Evaluation may be l
postponed indefinitely of Control Systems 1218 due to current plant GL E9-19 status l
A-48 Hydrogen Control 10 CFP 50.44 All, except N/A Measures and Effects SECY 89-172 PWRs with l
of Hydrogen Burns large dry on Safety Equipment containments A-49 Pressurized Themal PGs 1.154. 1.99 Pug C/
1-86 Initial PTS Submittal of Shock SECY 82-465 Jan.1986 was first SECY P.3-288 closure of this ongoing SECY 81-687 issue. GL 88-11 10 CFR 50.61/
response required t
additional action GL 88-11 k
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