ML19332D418
| ML19332D418 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/27/1989 |
| From: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, NUDOCS 8912010170 | |
| Download: ML19332D418 (6) | |
Text
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N David W. Cockfield Vice P. resident, Nuclear L 1
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. November 27. 1989:
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Docket 50-344 License NPF-1 b.
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Dear Sir:
me Generic Letter 89-21, Status of Implementation of Unresolved Safety Issue (USI) Requirements
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~ ~As requested by Generic Letter 89-21 dated October 19, 1989, attached i
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. please: find che status of implementation of-USIs applicable to the Trojan a:
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- Nuclear. Plant for which,a final technical resolution'has been. achieved.
Sincerely, q
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Attachment.
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' ic t Mr.' John B. Martint
.. Regional Administrator,. Region V
,yf U.S. 'Nu'elear Regulatory Comi'ssion s1 Mr. LDavid Stewart-Smith State of Oregon' Department'of Energy 1
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.Mr! R.'C.'Barr NRC: Resident. Inspector Trojan Nuclear Plant J.:-
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Subscribed and sworn to before me this 27th day of November, 1989.
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Notary Public of Oregon My. Commission Expires:
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License NPF-1 Attachmenti LPage-1 of 5
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TABLE 1 UNRESOLVED SAFETY ISSUES'FOR WHICH A YINAL TECHNICAL' RESOLUTION HAS BEEN ACHIEVED USI/MPA Reference Document /
Status /Date Number Title Generic Letter Applicability (C)(NC)(NA)(I)(E)
Remarks J..
A-1 Water Hammer SECY'84-119 All C, 12/23/80 1.
PCE ' letter dated.
NUREG-0927, Rev. 1
.12/23/80.
.2.
INPO-accreditation ^ '
Item I.A.2.3 of training.
SRP Revisions A-2/
Asymmetric Blowdown NUREG-0609.
PWR C-TNRC Safety Evaluation D-10 Loads on Reactor NUREG-0371 on Elimination of Pos--
Primary Coolant Systems GDC-4/84-04 tulated Primary. Loop' Pipe Ruptures asia
-Design Basis,-. dated 08/05/88.
A-3 Westinghouse Steam SECY.86-97 W-PWR NC Generator Tube Integrity -NUREG-0844/85-02 (No Requirements)
A-4 CE Steam Generator Tube NUREG-0844 CE-PWR N/A Integrity (No Requirements)
A-5 B&W Steam Generator Tube NUREG-0844 B&W-PWR N/A Integrity (No Requirements) l C - Complete
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EC - No Changes Necessary NA - Not Applicable L
I - Incomplete i
E - Evaluating Actions Required
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. Doctament Control' Eleskh Docket 50-344
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License-NPF-1 Attachment ~
Page 2~of 5 USI/MPA Reference Document /
Status /Date-Number Title Generic Letter Applicability (C)(NC)(NA)(I)(E)
Remarks-A-6 Mark I Short-Term NUREG-0408
' Mark I-BWR N/A Program A-7/
Mark I Long-Term NUREG-0661' Mark I-BWR N/A D-01 Program NUREG-0661, Suppl.-1/
79 A-8 Mark II Containment NUREG-0808 Mark'II-BWR' N/A~
Pool Dynamic Loads NUREG-0487,: Suppl. 1/2 NUREG-0802 l
SRP 6.2.1.1C GDC-16 A-9 Anticipated Transients NUREG-0460, Vol. 4 All I,~07/90 A1WS Mitigating' System Without Scram 10 CFR 50.62 actuation circuitry to be installed during.
1990 refueling outage.
A-10/
BWR Feedwater Nozzle NUREG-0371 BWR N/A B-25 Cracking NURSG-0619/ Letter from D.G. Eisenhut dated 11/13/80 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All C, 6/85 WCAP-10861, Analysis Toughness 10 CFR 50.60/82-26 of Capsule X from PGE Trojan Reactor Vessel Radiation Surveillance Program.
C - Complete NC - No Changes Necessary NA - Not Applicable I - Incomplete E - Evaluating Actions Required
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'Trojtn Nuclesr. Plant-Document Control'.' Desk-h '
~ Docket 50-344 November 27,' 1989.
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License NPF-1 Attachments.
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.-Page 3 of 5 1
USI/MPA Reference' Document /;
Status /Date' L
Number Title Generic Letter ~
. Applicability (C)(NC)(NA)(I)(E)
Remarks l-h-12 Fracture Toughness-of NUREG-0577,'Rev. 1
' PWR.
' N/A' l
Steam Generator and
- NUREG-0371 Reactor Coolant Pump NUREG--0606 l
Supports SRP Revision 5.3'.4 A-17 Systems Interaction NUREG-1174.NUREG-1229, Alln E, 12/31/89 NUREG/CR-3922 NUREG/CR-4261-
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NUREG/CR-4470 Generic Letter 89-18 (No Requirements)
A-24/
Qualification of Class
- NUREG-0588, Rev. 1 All C
1.
NRC Safety Evalu--
B-60 IE Safety-Related SRP 3.11 ation' dated-Equipment 10 CFR 50.49 12/04/84..
82-09, 84-24, 85-15 2.
PGE letter dated 01/28/85.
A-26/
Reactor Vessel Pressure NUREG-0224 PWR
- C, 12/06/82
- NRC Safety Evaluation B-04 Transient Protection
. dated 12/06/82 (Amend '
ment 78 to NPF-1).
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A-31 Residual Heat Removal NUREG-0371, NUREG-0606 All OLs After N/A-Shutdown Requirements Reg. Guide 1.113-01/79 Reg. Guide-1.139 SRP 5.4.7 C - Complete NC - No Changes Necessary NA - Not Applicable I - Incomplete E - Evaluating Actions Required
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'DocumenC Control Desk b,
--Docket 50-344 November 27,-1989':
u License NPF-1_
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'Page~4.of 5 y
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Status /Date-USI/MPA Reference Document /..
(C)(NC)(NA)(I)(E)'
Remarks
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Number Title Generic Letter'-
Applicability A-36/
Control of Heavy Loads NUREG-0612 iAll C, 06/24/84
. PGE letter dated C-10/
Near Spent Fuel SRP 9.1.5/81-07, 83-42, 06/24/84 M
C-15 Letter from D.G.
'Eisenhut dated 12/22/80-A-39 Determination of SRV NUREG-0802 BWR N/A s
Pool Dynamic Loads and NUREG-0661 and Pressure Transients SRP 6.2.1.1.c A-40 Seismic Design Criteria-
-SRP Revisions,.NUREG/
All E, 09/92; Only item 4'" design:
CR-4776, NUREC/CR-0054 of flexible vertical' NUREG/CR-3480, NUREG/-
tanks" is_ applicable'-
CR-1582 NUREG/CR-1161' to Trojan. The evalu-NUREG-1233, NUREG-4776 ation will-be in~;
NUREG/CR-3805, NUREG/
cluded in the evalu--
CR-5349, NUREG/CR-3509 ation for USI No.
'A-46.
l A-42/
Pipe Cracks in Boiling NUREG-0313. Rev. 1/
BWR N/A i
B-05 Water Reactors 81-03
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A-43 Containment Emergency NUREG-0510. NUREG-0869 PWR
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Sump Performance NUREG-0897 l
Reg. Guide 1.82 SRP. Revision /85-22 i
C - Complete NC - No Changes Necessary NA - Not Applicable I - Incomplete E - Evaluating Actions Required
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Trojan Nuclear Plant Docket 50-344 November 27, 1989 License NPF-1 Attachment Page 5 of-5 USI/MPA Reference Document /
Status /Date Number Title Generic Letter Applicability (C)(NC)(NA)(I)(E)
Reserks A-44 Station' Blackout Reg. Guide 1.155 All
- 12/91 Implesment procedure NUREG-1032, NUREG-1109 changes.
10 CFR 50.63 A-45 Shutdown Decay Heat.
NUREG-1289, NUREG-1292 All E, 09/92 Removal Requirements NUREG/CR-5230 SECY 88-260 (No Requirements)
A-46 Seismic Qualification NUREG-1030 All E, 09/92 of Equipment in NUREG-1211/87-02, Operating Plants 87-03 A-47 Safety Implication NUREG-1217, NUREG-1218 All E, 03/16/90 of Control Systems Generic Letter 89-19 A-48 Hydrogen Control 10 CFR 50.44 All, except N/A Measures and Effects FWRs with of Hydrogen Burns large dry containments A-49 Pressurized Thermal NUREG-0649 PWR E, 02/28/90 Shock Reg. Guides 1.154 and 1.99 10 CFR 50.61/88-11 C - Complete NC - No Changes Necessary i
NA - Not Applicable I - Incomplete E - Evaluating Actions Required 3033W.1189
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