L-90-216, Responds to Generic Ltr 90-04, Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions
| ML17348A364 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 06/27/1990 |
| From: | Harris K FLORIDA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-83-28, GL-88-14, GL-88-17, GL-90-03, GL-90-04, GL-90-3, GL-90-4, L-90-216, NUDOCS 9007060049 | |
| Download: ML17348A364 (27) | |
Text
P 0 bu ~ 14OGl,.Juno beai
~l 334OS OCiO APL JUN 27 1990 L-90-216 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
Re:
Turkey Point Units 3 and 4
Docket Nos.
50-250 and 50-251 Request for Information on the Status of Licensee Implementation of Generic Safety Issues Resolved with Imposition of Requirements or Corrective Actions Generic Letter 90-04 By Generic Letter
&0-04, dated April 25,
- 1990, the NRC staff requested that licensees review the status of, and provide documentation concerning the implementation status of the generic safety issues identified in Generic Letter 90-04.
The requested information for Turkey Point Units 3 and 4 is attached.
If further discussion is required on this topic, please contact us.
Very truly yours,
). l(,.,
K.
N Harris Vic President Tur ey Point Plant KNH/TCG/gp Attachment cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, Turkey Point Plant 90~i-Oi~~ 9C)0+ >7 PDR
- ADClCf,
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an FPl Gluop con'pun>
FACILITY NAME:
Turkey Point Unit 4 DOCKET NO.:
50-251 LICENSEE:
Florida Power and Light Co.
STATUS OF LICENSEE IMPLEMENTATION OF GFHERIC SAFETY ISSUES GSI MPA No.
40 (B065) 41 (B058')
43 (B107) 51 (L913)
TITLE Safety Concerns Associated With Pipe Breaks In The BWR Scram System BWR Scram Discharge Uolume Systems Reliability Of Air Systems Improving the Reliability of Open-Cycle Service Water Systems APPLICABILITY All BWRs All BWRs All Plants All Plants STATUS*
COMMENTS NA NA Note 1
L-90-29. dated Jan.
30, 1990
- 67. 3. 3 (A017) 75** (B076) 75 (B085)
Improved Accident Monitoring Item 1.1
- Post-Trip Review (Program Description and Procedure)
Item 1.2
- Post-Trip Review-Data and Information Capability All Plants All Plants All Plants I (12/90)
Note 2
Note 3
Note 3
- Please follow attached guidance for completing this column.
Item numbers correspond to Generic Letter 83-28 action item numbers.
2
~GSI MPA
~No 75 (B077) 75 (B086) 75 (L003)
TITLE Item 2.1
- Equipment Classi-fication and Vendor Interface (Reactor Trip System Components)
Item 2.2.1
- Equipment Classifi-cation for Safety-Related Components Item 2.2.2
- Vendor Interface for Safety-Related Components APPLICABILITY All Plants All Plants All Plants STATUS*
NMENTS Note 3
Notes 3,
5 Notes 3, 5
75 (B078)
Items 3.1.1
& 3.1.2
- Post-Maintenance Testing (Reactor Trip System Components)
All Plants Note 3
75 (B079)
Item 3.1.3
- Post-Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components)
All Plants Note 3
75 (B087)
Items 3.2.1
& 3.2.2
- Post-Maintenance Testing (All Other Safety-Related Components)
All Plants I (9/1/90)
Note 3
75 (B088)
Item 3.2.3
- Post-Maintenance Testing-Changes to Test Require-ments (All Other Safety-Related Components)
All Plants Note 3
75 (B080)
Item 4.1
- Reactor Trip System Reliability (Vendor-Related Modifications)
All Plants Note 3
75 (B081)
TITLE Items 4.2.1
& 4.2.2
- Reactor Trip System Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
APPLICABILITY All PWRs STATUS*
COMMENTS Note 3
75 (B082)
Item 4.3
- Reactor Trip System Reliability - Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
All W and B&W Plants Note 3
75 (B090)
Item 4.3
- Reactor Trip System Reliability - Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment For Westinghouse and BW Plants)
All W & B&W Plants Notes 3,
5 75 (B091)
Item 4.4
- Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)
All B&W Plants NA
4 GSI/(MPA ~No 75 (B092) 75 (B093) 86 (B084) 93 (B098)
TITLE Item 4.5.1
- Reactor Trip System Reliability-Diverse Trip Features (System Functional Testing)
Items 4.5.2
& 4.5.3
- Reactor Trip System Reliability - Test Alterna-tives and Intervals (System Functional Testing)
Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Steam Binding of Auxiliary Feedwater Pumps APPLICABILITY All Plants All Plants All BWRs All PWRs STATUS*
NA COMMENTS Note 3
Note 3
L-88-237, dated May 24, 1988 99 (L817)
RCS/RHR Suction Line Valve Interlock on PWRs All PWRs Notes 4, 5
124 Auxiliary Feedwater System Reliability AN0-1&2, Rancho Seco, Prairie Island 1&2, Crystal River-3 Ft. Calhoun-NA A-13 (B017)
Snubber Operability Assurance-Hydraulic Snubbers All Plants NA See 8022 Hydraulic snubbers have been replaced with mechanical snubbers
5
~GSI MPA ~No.
A-13 (B022)
A-16 (D012)
A-35 (B023)
TITLE Snubber Operability Assurance Mechanical Snubbers Steam Effects on BWR Core Spray Distribution Adequacy of Offsite Power Systems APPLICABILITY All Plants Oyster Creek
& NMP-1 All Plants STATUS*
NA t'OMMENTS Amend 90, dated Oct 14, 1983 Amend 98, dated Aug 14, 1984 B-10 Behavior of BWR Mark III Containments All BWR Mark III NA Plants B-36 Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Uentilation Systems All Plants with OL Applications After 4/1/80 NA B-63 (B045)
Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary All Plants Order dated April 20, 1981 L-87-264, dated June 23, 1987
NOTES In letter L-90-197 dated May 30,
- 1990, FPL reported that the design and operations verification of the instrument air
- system, as required by GL 88-14 was complete.
Schedules for action items resulting from the required verification are stated in that letter.
2.
3
~
4
~
5.
The Area Radiation Monitoring System upgrade will be completed by December 31, 1990.
An NRC review of compliance with Regulatory Guide 1.97 requirements was included in NRC Inspection Report 50-250/90-01 and 50-251/90-01 dated February 2,
1990.
A detailed status of implementation of required actions based on the generic implications of the ATWS events at the Salem Nuclear Plant was provided by FPL in letter L-90-95 dated April 5, 1990.
FPL is reviewing GL 90-03, Relaxation of Staff Position in Generic Letter 83-28, Item 2.2, Part 2,
"Vendor Interface for Safety-Related Components",
and will provide a
response by September 29, 1990.
FPL's response to GL 88-17, "Loss of Decay Heat Removal",
was provided in letters L-88-559 dated January 3,
1989 and February 1,
1989.
Required action items and schedules for their completion were identified in that letter.
The NRC has not yet completed its review of this item.
FACILITY NAME: Turke Point Unit 4 DOCKET NO.:
1 ilCENSEE: ~Pi ht C
GSI Status Summar ENCLOSURE 2
~
m GSI/MPA No.
40 (B065)
Title Safety Concerns Associated With Pipe Breaks In The BWR Scram System Licensee Status Determination N/A Staff Status Determination N/A Remarks 41 (B058) 43 (8107) 51 (L913)
BWR Scram Discharge N/A Volume Systems Reliability Of Air Systems Improving the Reliability of Open-Cycle Servi ce Water Systems N/A Licensee met requirements of GL 88-14 by letter dated 5/30/90.
Licensee still implementing identified improvements.
Expect to complete by 12/07/90.
Licensee response dated 1/30/90 established the required 5
programs.
All additional actions such as reviews or inspections to carry out the programs, are scheduled and documented in t/30/90 lette'r al1,to be complete ~
by restart from dual unit outage ending in 12/91.
67.3.3 (A017)
Improved Accident Monitoring I/12-90 I/12-90 RG 1.97 implementation inspected in IR 90-01 and found acceptable.
Area Rad. Monitoring System upgrade to be complete 12/31/90.
Exception for ARMS had been re-3 quested to permit a range ~f 10 4
to 10 R/hr instead of 10 to 10 Licensee will withdraw request for exception and meet RG 1.97 by 12/31/90.
GS I/HPA No.
75** (8076) 75 (B085) 75 (B077) 75 (B086) 75 (L003) 75 (B078)
Title Item 1.1 - Post-Trip Review (Program Description and Procedure)
Item 1.2 - Post-Trip Review - Data and Information Capability Item 2.1 - Equipment Classification and Vendor Interface (Reactor Trip System Components)
Item 2.2.1 - Equipment Classification for Saf ety-Re 1 ated Components Item 2.2.2 - Vendor Interface for Safety-Related Components Items 3.1.1
& 3.1.2-Post - Maintenance Testing (Reactor Trip System Components)
Licensee Status Determination Staff Status Determination C 8/15/85 C 4/17/87 C 4/17/87 E/09-29-90 C 7/31/86 C
C 5/31/85 Remarks Licensee implementation complete.
Staff issued SER 8/09/90.
GL 90-03 supercedes 2.2.2.
- The dates shown for the Salem ATWS items are contained in a 4/5/90 letter from the licensee.
GSI/MPA No.
75 (B079)
Title Item 3.1.3 - Post-Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components)
Licensee Status Determination Staff Status Determination C 7/31/86 Remar ks 75 (B087) 75 (B088) 75 (B080)
Items 3.2.1 5 3.2.2-Post-Maintenance Testing (All Othe~
Safety-Related Components)
Item 3.2.3 - Post-Maintenance Testing-Changes to Test Requirements (All Other Safety-Related Components)
Item 4.1 - Reactor Trip System Reliability (Vendor-Related Modifications)
I/9-1-90 I/10/15/90 C 7/31/86 C 11/8/83 Licensee has indicated verbally item was completed about 9/1/90. ~
Letter to NRC documenting completion expected by 10/15/90.
SER dated ll/14/85.
0
GSI/MPA No.
75 (B081)
Title Licensee Status Determination Staff Status Determination C
C 1/18/85 Items 4.2.1
& 4.2.2-Reactor Trip System Reliability-Maintenance and Testing (Preventative Maintenance and
.Surveillance Program for Reactor Trip Breakers)
Remarks 75 (8082) 75 (B090) 75 (B091)
Item 4.3 - Reactor Trip System Reliability-Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
Item 4.3 - Reactor Trip System Reliability-Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment For Westinghouse and B&W Plants)
Item 4.4 - Reactor Trip System Reliability
( Improvements in Maintenance and Test Procedures for B&W Plants)
N/A C 6/30/86 C 12/31/87 N/A Licensee's design accepted by NRC.
TS are part of the TS upgrade amendment issued 8/28/90.
Implementation required by 8/28/91.
TS have been implemented in 1987 by administrative procedure.
GSI/HPA No.
75 (B092) 75 (B093) 86 (B084) 93 (B098) 99 (L817) 124 A-13 (B017)
Titie Item 4.5.1 - Reactor Trip System Re 1 iab i 1 ity-Diverse Trip Features (System Functional Testing)
Items 4.5.2 8 4.5.3-Reactor Trip System Reliability-Test Alternatives and Intervals (System Functional Testing)
Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Steam Binding of Auxiliary Feedwater Pumps RCS/RHR Suction Line Valve Interlock on PWRs Auxiliary Feedwater System Rel iabi 1 ity Snubber Operability Assurance-Hydraulic Snubbers Licensee Status Determination N/A N/A N/A Staff Status Determination C 5/1/86 C 5/1/86 N/A C 5/24/88 I 12/91 N/A-N/A Remarks NRC letter dated 6/15/88.
GL 88-17, Licensee actions/
schedules provided in letters dated 1/3/89, 2/1/89.
Staff review not complete.
Imple-mentation expected to be complete 12/91.
GSI/MPA No.
A-13 (B022)
A-16 (D012)
A-35 (8023)
B-10 B-36 Tit1e Snubber Operability Assurance - Mechanical Snubbers Steam Effects on BWR Core Spray Distribution Adequacy of Offsite Power Systems Behavior of BWR Hark III Containments Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems Licensee Status Determination N/A N/A N/A Staff Status Determination C 10/14/83 N/A C 5/10/84 N/A N/A Remarks Amendments 96 and 90 for Units 3 and 4
Licensee (G. Salamon) indicated verbally that Plant Change Modification b'80-44 dated 5/10/84 was completed.
See also FPL letter L-85-347 to J.
Nelson Grace (Region II) dated 9/3/85, "10 CFR 50.59 Report."
GSI/HPA No.
B-63 (B045)
Title Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary Licensee Status Determination Staff Status Determination C 4/20/81 Remarks Item 99 (L817)
(cont)
Status RCS/RHR Suction Line Valve Interlock on PWRs (7) Provide permanent scale in containment for Tygon tube level indication Both reactor units will shut down beginning in late 1990, for about a year or more, to install two additional diesel generators.
Implementation of the above modifications wi 11 proceed during the outage.
All implementation on this issue is expected to be complete by 12/91.
This is an acceptable schedule.
Gordon E. Edison, Sr. Project Hanager Project Directorate II-2 Division of Reactor Projects I/II
Enclosures:
As stated
FACILITY NAME: Turke Point Unit 4
=DOCKET NO.:
1 LICENEEE: ~Liht C
GSI Status Summar ENCLOSURE 2
4 GSI/MPA No.
40 (B065)
Titie Safety Concerns Associated With Pipe Breaks In The BWR Scram System Licensee Status Determination N/A Staff Status Determination N/A Remarks 41 (B058) 43 (B107) 51 (L913)
BWR Scram Discharge N/A Volume Systems Reliability Of Air Systems Improving the Reliability of Open-Cycle Service Water Systems N/A Licensee met requirements of GL 88-14 by letter dated 5/30/90.
Licensee still implementing identified improvements.
Expect to complete by 12/07/90.
Licensee response dated 1/30/90 established the required 5
programs.
All additional actions such as reviews or inspections to carry out the programs, are scheduled and documented in 1/30/90 Iettev, a1'I to be complete ~
by restart from dual unit outage ending in 12/91.
67.3.3 (A017)
Improved Accident Monitoring I/12-90 I/12-90 RG 1.97 implementation inspected in IR 90-01 and found acceptable.
Area Rad. Monitoring System upgrade to be complete 12/31/90.
Exception for ARMS had been re-3 quested to permit a range ~f 10 to 10 R/hr instead of 10 to 10 Licensee will withdraw request for exception and meet RG 1.97 by 12/31/90.
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GSI/NPA No.
Title Licensee Status Determination Staff Status Determination Remarks 75** (B076) 75 (8085) 75 (B077) 75 (B086) 75 (L003) 75 (B078)
Item 1.1 - Post-Trip Review (Program Description and Procedure)
Item 1.2 - Post-Trip Review - Data and Information Capability Item 2.1 - Equipment Classification and Vendor Interface (Reactor Trip System Components)
Item 2.2.1 - Equipment Classification for Saf ety-Related Components Item 2.2.2 - Vendor Interface for Saf ety-Related Components Items 3.1.1 5 3.1.2-Post - Maintenance Testing (Reactor Trip System Components)
C C 5/31/85 C 8/15/85 C 4/17/87 C 4/17/87 E/09-29-90 7/31/86 Licensee implementation complete.
Staff issued SER 8/09/90.
GL 90-03 supercedes 2.2.2.
- The dates shown for the Salem ATMS items are contained in a 4/5/90 letter from the licensee.
GSI/MPA No.
75 (8079)
Title Item 3.1.3 - Post-Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components)
Licensee Status Determination Staff Status Determination C 7/31/86 Remar ks 75 (B087) 75 (B088) 75 (B080)
Items 3.2.1 In 3.2.2-Post-Maintenance Testing (All Other Safety-Related Components)
Item 3.2.3 - Post-Maintenance Testing-Changes to Test Requirements (All Other Safety-Related Components)
Item 4.1 - Reactor Trip System Reliability (Vendor-Related Modifications)
I/9-1-90 I/10/15/90 C 7/31/86 C 11/8/83 Licensee has indicated verbally item was completed about 9/1/90.
Letter to NRC documenting completion expected by 10/15/90.
SER dated ll/14/85.
GSI/I'IPA No.
75 (B081) 75 (B082) 75 (B090)
Title Items 4.2.1
& 4.2.2-Reactor Trip System Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
Item 4.3 - Reactor Trip System Reliability-Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants)
Item 4.3 - Reactor Trip System Reliability-Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment For Westinghouse and B&H Plants)
-Licensee Status Determination Staff Status Determination C 1/18/85 C 6/30/86 C 12/31/87 Remarks Licensee's design accepted by NRC.
TS are part of the TS upgrade amendment issued 8/28/90.
Implementation required by 8/28/91.
TS have been implemented in 1987 by administrative procedure.
75 (B091)
Item 4.4 - Reactor Trip System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)
N/A N/A
GSI/NPA No.
75 (8092) 75 (B093) 86 (B084) 93 (B098) 99 (L817) 124 A-13 (B017)
Title Item 4.5.1 - Reactor Trip System Reliability-Diverse Trip Features (System Functional Testing)
Items 4.5.2 5 4.5.3-Reactor Trip System Reliability-Test Alternatives and Intervals (System Functional Testing)
Long Range Plan for Dealing with Stress Corrosion Cracking in BWR Piping Steam Binding of Auxiliary Feedwater Pumps RCS/RHR Suction Line Valve Interlock on PWRs Auxiliary Feedwater System Reliability Snubber Operability Assurance-Hydraulic Snubbers Licensee Status Determination N/A N/A N/A Staff Status Determination C 5/1/86 C 5/1/86 N/A C 5/24/88 I 12/91 N/A N/A Remarks NRC letter dated 6/15/88.
GL 88-17, Licensee actions/
schedules provided in letters dated 1/3/89, 2/1/89.
Staff review not complete.
Imple-mentation expected to be complete 12/91.
P
~
Vg GSI/MPA No.
A-13 (B022)
A-16 (D012)
A-35 (B023)
B-10 B-36 Title Snubber Operability Assurance - Mechanical Snubbers Steam Effects on BWR Core Spray Distribution Adequacy of Offsite Power Systems Behavior of BWR Mark III Containments Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems Licensee Status Determination N/A N/A N/A Staff Status Determination C 10/14/83 N/A C 5/10/84 N/A N/A Remarks Amendments 96 and 90 for Units 3 and 4 Licensee (G. Salamon) indicated verbally that Plant Change Modification 880-44 dated 5/10/84 was completed.
See also FPL letter L-85-347 to J.
Nelson Grace (Region II) dated 9/3/85, "IO CFR 50.59 Report."
GSI/MPA No.
Title Licensee Status Determination Staff Status Determination Remarks B-63 (B045)
Isolation of Low Pressure Systems Connected to the Reactor Coolant System Pressure Boundary C
C 4/20/81
Item 99 (L817)
(cont)
Status RCS/RHR Suction Line-Valve-Interlock-on-PWRs (7) Provide permanent scale in containment for Tygon tube level indication Both reactor units will shut down beginning in late 1990, for about a year or more, to install two additional diesel generators.
Implementation of the above modifications wi 11 proceed during the outage.
All implementation on this issue is expected to be complete by 12/91.
This is an acceptable schedule.
Enclosures:
As stated Original signed by Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects I/II DISTRIBUTION
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Docket No. 50-251 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 October 1, 1990 MEMORANDUM FOR:
Docket File FROM:
SUBJECT:
Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects - I/II STATUS OF RESOLVED GENERIC SAFETY ISSUE IMPLEMENTATION RE(UIREMENTS AT TURKEY POINT UNIT 4 The current status of resolved Generic Safety Issue (GSI) Implementation Requirements at the Turkey Point 4 facility is summarized in the enclosures to this memorandum.
Enclosure 1 contains a copy of the information provided by the licensee in its response to Generic Letter 90-04.
Enclosure 2 is a status summary for each GSI applicable to this facility.
This status summary is based upon the licensee's response to the Generic Letter, discussions with the licensee and cognizant staff and my review of available NRC records and information.
Those items considered to be incomplete 'are listed below together with my assessment of the significance of that status and of the licensee's plans for completion.
Item Status 43 (B107)
- 51 (L913)
Reliabilit of Air S stems In a letter dated 7/25/90 the staff notified the licensee that they had met the requirements of GL 88-14 with their response dated 5/30/90.
Licensee will complete implementation of identified improvements by December 7, 1990.
Im rovin the Reliabilit of 0 en-C cle Service Mater
~Sstems Licensee response dated 1/30/90 established the required 5 programs with schedules to carry out additional actions such as reviews or inspections.
All implementation to be complete by restart from dual unit outage (about 12/91).
Item 67.3.3 (A017) 75 (L003) 75 (B087) 99 (L817)
Status Im roved Accident Monitorin NRC Inspection Report 90-01, dated 2/12/90, reviewed compliance with RG 1.97.
The results of the inspection were that the licensee satisfactorily met the require-ments and intent of RG 1.97 guidelines.
Last instrumen-tation to be upgraded (Area Radiation hlonitoring) will be implemented by 12/90.
This is an acceptable sc)edule.
Licensee had requested relief from 10 to 10 Rjhr range requirement.
Licensee subsequently is planning to withdraw request and meet the requirement.
Salem ATWS Item 2.2.2 - Vendor Interface for Safet Re a
e Com onen s
Recent guidance (GL 90-03) issued 3/20/90 by staff.
Licensee response expected by 9/29/90.
This is an acceptable schedule.
Salem ATWS Items 3.2.1 5 3.2.2 - Post Maintenance estrin ot er a
e e ate om onents Licensee has indicated verbally (G. Salamon to G. Edison) on 9/7/90 that these items were completed about 9/1/90, and a letter to NRC is in preparation to document the completion of implementation.
The letter is expected by 10/15/90 and this is an acceptable schedule.
RCS/RHR Suction Line Valve Interlock on PWRs Licensee actions and schedules responding to GL 88-17 were provided in letters dated 1/3/89 and 2/1/89.
Staff review is not complete.
Licensee is in process of modifications, including:
(1)
RCS level system (alarms in C.R.,
and transducers)
- 2) Correlation for intermediate-to-hot-leg level
- 3) Installation of redundant independent level channel 4)
RCS temperature indication 5)
RHR flow indication (6) Review Westinghouse Owners Group analyses and incorporate
Item 99 (L817)
(cont)
Status RCS/RMR Suction Line Valve Interlock on PMRs (7) Provide permanent scale in containment for Tygon tube level indication Both reactor units will shut down beginning in late 1990, for about a year or more, to install two additional diesel generators.
Implementation of the above modifications will proceed during the outage.
All implementation on this issue is expected to be complete by 12/91.
This is an acceptable schedule.
Enclosures:
As stated Original signed by Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects I/II DISTRIBUTION
~g GEdison DMiller RScholl OFC:PN:PDII-2 )~+:0:PDII-2 W
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