ML20055F691
| ML20055F691 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/13/1990 |
| From: | Cross J PORTLAND GENERAL ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-90-04, GL-90-4, NUDOCS 9007190040 | |
| Download: ML20055F691 (10) | |
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Nh BectricCoriguny James E. Cross Vice President Nuclear July 13, 1990 Trojan Nuclear plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Consission Attn Document Control Desk Washington DC 20555 i
Dear Sirst Generic Letter 90-04. Raquest for Information on the Status of Implementation of Generic Safety Issues (CSIs)
_ Resolved With imposition of Requirements ot* Corrective Actions As requested by Generic Letter 90-04 dated April 25, 1990, attached please find the status of implementation of CSIs applie.able to the Trojan Nuclear plant for which a final technical resolution has been achieved. The information regarding status is based solely on a review of documentation.
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Sincerely, l
{ 0:e Attachment l
c Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Cons.ission Mr. David Stewart-Smith State of Oregon Department of Energy Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear plant 0
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Trojsn Nuc1ccr Picnt Document Control Desk Docket 50-344 July 13, 1990 License NPF-1 Attachment Page 1 of 9 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES (GSIs) RESOLVED WITH IMPOSITION OF REQUIREMENTS OR COERECTIVE ACTIONS
_ftSI/MPA Number _
Title Agglicability
_ Status c-
-- t m 40 (B065)
Safety Concerns Associated With All BWRs N/A Pipe Breaks In the BWR Scram System 41 (B058)
BWR Scram Discharge Volume Systems All BWRs N/A 43 (B107)
Reliability of Air Systems All Plants I,
Final approval of Design 02/91 Basis Document on Instrument and Service Air and documentation of evaluation of need to inspect joint outside Containment still in progress.
(Ref: PCE to NRC letter dated February 3, 1989; August 31, 1989; November 30, 1989; and July 6, 1990.)
51 (L913)
Improving the Reliability of Open-All Plants I,
All items still in progress.
Cycle Service Water Systems 1971 (Ref: PGE to NRC letter Refuel-dated January 25, 1990) ing Outage STATUS CODES:
N/A - Not applicable to Trojan.
I - Changes not fully implemented; projected month and year of completion.
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au Document Contr:!;1 Desk Trojan Nuclear Plant.
July 13 1990 Docket 50-344 Attachment
- License NPF-1 Page 2 of 9 STATUS'0F LICENSEE-IMPLEMENTATION OF GENERIC SAFETY ISSUES (GSIs) RESOLVED WITH IMPOSITION OF REOUTREMENTS OR cnanFCTIVE ACTIM Title Applicability
_Siatus_
Comments
__GSIhfPA Number _
67.3.3 (A017)
Improved Accident Monitoring All Plants I,
Expected completion date is 10/90 based on the date the neutron flux recorders will be installed and the final resolution of the instrument redundancy issue will be determined.
(Ref: NRC Safety Evaluation Report dated September 29, 1986, PCE to NRC letters dated January 26, 1987; October 14, 1988; and May 31, 1990. NRC Inspection Report 88-36 dated September 16, 1988.)
75** (B076)
Item 1.1 - Post-Trip Review All Plants C
PGE to NRC letters dated November 4,1983 and (Program Description and Procedure)
July 19, 1985. NRC to PGE letter dated January 26, 1985. NRC Safety Evaluation Report dated September 5, 1985.
t Item
tumbers correspond to Generic Letter 83-28 action item numbers.
i STATUS CODES:
C - Complete.
fully i:splemented; project'.ed month and year of completJon.
I - Changes not
Trojan Nucle:tr Plcnt Document Control Desk Docket 50-344 July 13, 1990 Liccuse NPF-1 Attachment Page 3 of 9 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES LGSIs) RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS GSI/MPA Number _
Title Applicability JLatus c-tm 75 (B085)
Item 1.2 - Post-Trip Review -
All Plants C*
PGE to NRC letter dated (Data and Information Capability)
November 4, 1983.
75 (B077)
Item 2.1 - Equipment Classification All Plants I,
Expected completion date is.
and Vendor Interface (Reactor Trip 10/90 based on incorporation of Sys'.es Components) periodic communication with the Nuclear Steam Supply System Vendor in the vendor-interface program. PGE to NRC letter dated November 4, 1983.
75 (B086)
Item 2.2.1 - Equipment Classifi-All Plants C*
PGE to NRC letter dated cation for Safety-Lelated November 4, 1983.
Components 75 (LOO 3)
Item 2.2.2 - Vendor Interface for All Plants I,
Expected completion date is Safety-Related Components 09/90 the date the response to Generic Letter 90-03 will be.
submitted.
(Ref: PGE to NRC letters dated November 4, 1983, May 9, 1984, and June 14, 1985.)
STATUS CODES:
C - Complete.
C* - NRC Safety Evaluation Report has not been received.
I - Changes not fully implemented; projected month and year of completion.
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r Traj:n Nuclear Pltnt Document Control Desk'.
Docket 50-344 July 13,1990 -
Liecuse NPF-1 Attachment Page 4 of 9 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES (GSIs) RESOLVED WITH IMPOSITION OF ltXQUIREMENTS GR CORRECTIVE ACTIONS GSI/MPA Number _
Title A;plicability Status._
Cr nts 75 (B078)
Items 3.1.1 and 3.1.2 - Post-A L1 Plants C
PGE to NRC letters dated Maintenance Testing (Reactor November 4,1983 and Trip System Components)
July 19, 1985. NRC Safety Evaluation Report dated October 11, 1985.
75 (B079)
Item 3.1.3 - Post-Maintenance All Plants C*
PCE to NRC letters dated Testing-Changes to Test Require-November 4, 1983 and ments (Reactor Trip System October 13, 1986.
Components) 75 (B087)
Items 3.2.1 and 3.2.2 - Post-All Plants C
PGE to NRC letters dated l
Maintenance Tesiing (All Other November 4,1983 July 19, Safety-Related Components) 1985, and October 17, 1985. NRC Safety Evaluation Report dated February 12, 1986.
75 (B088)
Item 3.2.3 - Post-Maintenance All Plants C*
PGE to NRC letters dated Testing-Changes to Test Require-November 4, 1983 and
~
ments (All Other Safety-Related October 13, 1986.
Components)
STATUS CODES C - Complete.
C* - NRC Safety Evaluation Report has not been received.
u-LTrojan Nucicer Plcat Document Control Desk. -
Docket 50-344 July 13,'1990
' License NPF-1 Attachment Page 5 of 9 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES l
(GSIs) RESOLVED WITH IMPOSITION OF REOUIRFMENTS OR LORRECIlYE_ ACTIONS GSI/MPA Nn=her Title Anolicability Status
_Casmaants 75 (B080)
Item 4.1 - Reactor Trip System All. Plants C
PGE to NRC letters dated Reliability (Vendor-Related November 4,1983 and Modifications)
July 19, 1985. NRC Safety Evaluation Report dated cctober 10, 1985.
75 (B081)
Items 4.2.1 and 4.2.2 - Reactor All PWRs C
PGE to NRC letters dated Trip System Reliability-November 4, 1983 and Maintenance and Testing (Prevent-July 19, 1985. NRC ative Maintenance and Surveillance Safety Evaluation Report Program for Reactor Trip Breakers) dated August 27, 1985.
75 (B082)
Item 4.3 - Reactor Trip System All W and B&W C
PGE to NRC letters dated Reliability - Design Modifications Plants November 4,1983 and (Automatic Actuation of Shunt Trip March 30, 1984 NRC Attachment for Westinghouse and Safety Evaluation Report B&W Plants) dated July 26, 1984.
75 (B090)
Item 4.3 - Reactor Trip System All W and B&W C
PGE to NRC letters dated i
Reliability - Technical Specifi-Plants November 4, 1983, cation Changes (Automatic Actu-October 30, 1985, and ation of Shunt Trip Attachment June 22, 1987. NRC Safety for Westinghouse and B&W Plants)
Evaluation Report dated 1987 (NPF-1 Amendment -137).
STATUS CODES:
C - Complete.
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u Trojrn Nuc1c r Plcnt Document Control Desk
. Docket 50-344 July 13, 1990 Liccnse NPF-1 Attachment Page 6 of 9 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES (GSIs) RESOLVED WITH IMPOSITION OF REOUIREMENTS OR CORRECTIVE ACTIONS GSI/MPA Number Title Analicability
_ Status __
Comments 1
75 (B091)
Item 4.4 - Reactor Trip System All B&W Plants N/A Reliability (Improvement in Maintenance and Test Procedures for B&W Plants) 75 (B092)
Item 4.5.1 - Reactor Trip System All Plants C
PGE to NRC letter dated Reliability-Diverse Trip Features November 4,1983. NRC (System Functional Testing)
Safety Evaluation Report dated July 11, 1985.
75 (B093)
Items 4.5.2 and 4.5.3 - Reactor All Plants C
PGE to NRC letter dated i
Trip System Reliability - Test November 4, 1983. NRC Alternation and Intervals (System Safety Evaluation Reports Functional Testing) dated March 2, 1987 (Item 4.5.2) and August 10, 1989 (Item 4.5.3).
86 (B084) long Range Plan for Dealing with All BWRs N/A Stress Corrosion Cracking in BWR Piping.
STATUS CODES:
N/A - Not applicable to Trojan.
C - Complete.
J-'
Trajnn Nuclear Plcnt Document Control Desk '+
. Docket 50-344-July 13, 1990
~Liccuse NPF-1
. Attachment.
Page 7 of 9 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES (GSIs) RESOLVED WITH IMPOSITION OF REQUIREMENTS OR CORRECTIVE ACTIONS CSI/MPA Nu=her_
Title Applicability
_ Status C.
tm 93'(B098)
Steam Binding of Auxiliary Feed-All PWRs C
PGE to NRC letters dated water Pumps February 28, 1986 and May 24, 1988. Generic Letter 88-03 dated June 8, 1988 acknowledges adequete-response.
99 (L817)
RCS/RHR Suction Line Valve All PWRs I,
Per WCAP 11736 and assoc 1-Interlock on PWRs 1994 ated NRC Safety Evaluation Refuel-Report, removal of the RBR ing suction auto-closure Outage interlock is being assessed as part of the Individual Plant Kwamination Prob-abilistic Risk Assessment.
Dalete interlock if appropriate. FGE to NRC letter dated March 30, 1990.
124 Auxiliary Feedwater System ANO-1 and 2, N/A Reliability Rancho Seco, Prairie Island 1 and 2, Crystal River-3, Ft. Calhoun
.CTATUS CODES:
l l
N/A - Not applicable to Trojan.
C - Coniplete.
I - Changes not fully implemented; projected month and year of. completion.
.3 Document Contr:1 Desk-..
Trojan Nuclear Plant.
July 13, 1990 Docket 50-344 Attachment Liccuse NPF-1 Page 8 of 9 STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES IGSIs) RESOLVED WITH IMPOSITION OF REOUTurnorIS _Olit ensart'TIVE ACTIONS GSI/MPA Nu=her_
Title Agglicabilitir Status _
C<
=ts A-13 (B017)'
Snubber Operability Assurance -
All Plants C
NRC Safety Evaluation Report dated February 6, 1985 Hydraulic Snubbers (NPF-1 Amendment 102).
A-13 (B022)
Snubber Operability Assurance -
All Plants C
MRC Safety Evaluation Report dated February 6, 1985 Mechanical Snubbers (NPF-1 Amendment 102).
A-16 (D012)
Steam Effects on BWR Core Spray Oyster Creek N/A j
j Distribution.
and ICIP-1 A-35 (B023)
Adequacy of Offsite Power All Plants C*
License Amendment 57 was issued on April 16, 1981.
Systems In the submittal letter for the amendment the NEC stated the issuance of the amendment and related safety evaluation completes the technical evaluation of the generic issue. See subse-quent NRC letter to PGE dated May 5,1982 for resolution of request for diesel generator test. PGE will be reevaluating this issue in the next 3 months.
STATUS CODES:
N/A - Not applicable to Trojan.
C - Complete.
C* - Issue to be reevaluated.
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- Trojan Nuclect Plmt Document Control Desk -~ o Docket 50-344 July 13, 1990 License NPF-1 Attachment Page 9 of'9
- STATUS OF LICENSEE IMPLEMENTATION OF GENERIC SAFETY ISSUES IGEls) nRMLVED WITH IMPOSITION OF RENJInK8EETS OR NwTIVE ACTIONS GSI/MPA Number Title Applicabili!;y Status Cr als B-10 Behavior of BWR Mark III All EER N/A Containments Mark III Plants B-36 Develop Design, Testing and All Plants N/A Maintenance Criteria for with OL Atmosphere Cleanup System Applications Air Filtration and Absorption After Units for Engineered Safety 04/01/80 Features Systems and for Normal Ventilation Systems B-63 (BO45)
Isolation of Iow Pressure All Plants C
Order of Modification of Systems Connected to the License NPF-1 dated Reacter Coolant System April 20, 1981.
Pressure Boundary STATUS CODES:
N/A - Not applicable to Trojan.
C - Complete.
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