ML17348A364

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,

).K. l(,.,

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 600250 PDR ADClCf, <3.

p l-'

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. TITLE APPLICABILITY STATUS* COMMENTS 40 (B065) Safety Concerns Associated With All BWRs NA Pipe Breaks In The BWR Scram System 41 (B058') BWR Scram Discharge Uolume Systems All BWRs NA 43 (B107) Reliability Of Air Systems All Plants Note 1 51 (L913) Improving the Reliability of All Plants L-90-29. dated Open-Cycle Service Water Systems Jan. 30, 1990

67. 3. 3 (A017) Improved Accident Monitoring All Plants I (12/90) Note 2 75** (B076) Item 1.1 - Post-Trip Review All Plants Note 3 (Program Description and Procedure) 75 (B085) Item 1.2 - Post-Trip Review- All Plants Note 3 Data and Information Capability

• Please follow attached guidance for completing this column.

• • The 16 items listed for GSI 75 all relate to actions derived from the generic implications of Salem ATWS events.

Item numbers correspond to Generic Letter 83-28 action item numbers.

2

~GSI MPA ~No TITLE APPLICABILITY STATUS* NMENTS 75 (B077) Item 2.1 - Equipment Classi- All Plants Note 3 fication and Vendor Interface (Reactor Trip System Components) 75 (B086) Item 2.2.1 - Equipment Classifi- All Plants Notes 3, 5 cation for Safety-Related Components 75 (L003) Item 2.2.2 - Vendor Interface All Plants Notes 3, 5 for Safety-Related Components 75 (B078) Items 3.1.1 & 3.1.2 - Post- All Plants Note 3 Maintenance Testing (Reactor Trip System Components) 75 (B079) Item 3.1.3 - Post-Maintenance All Plants Note 3 Testing-Changes to Test Require-ments (Reactor Trip System Components) 75 (B087) Items 3.2.1 & 3.2.2 - Post- All Plants I (9/1/90) Note 3 Maintenance Testing (All Other Safety-Related Components) 75 (B088) Item 3.2.3 - Post-Maintenance All Plants Note 3 Testing-Changes to Test Require-ments (All Other Safety-Related Components) 75 (B080) Item 4.1 - Reactor Trip System All Plants Note 3 Reliability (Vendor-Related Modifications)

3 GSI MPA No. TITLE APPLICABILITY STATUS* COMMENTS 75 (B081) Items 4.2.1 & 4.2.2 - Reactor All PWRs Note 3 Trip System Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (B082) Item 4.3 - Reactor Trip System All W and B&W Note 3 Reliability - Design Modifications Plants (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B090) Item 4.3 - Reactor Trip System All W & B&W Notes 3, 5 Reliability - Tech Spec Changes Plants (Automatic Actuation of Shunt Trip Attachment For Westinghouse and BW Plants) 75 (B091) Item 4.4 - Reactor Trip System All B&W Plants NA Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)

4 GSI/(MPA ~No TITLE APPLICABILITY STATUS* COMMENTS 75 (B092) Item 4.5.1 - Reactor Trip System All Plants Note 3 Reliability-Diverse Trip Features (System Functional Testing) 75 (B093) Items 4.5.2 & 4.5.3 - Reactor Trip All Plants Note 3 System Reliability - Test Alterna-tives and Intervals (System Functional Testing) 86 (B084) Long Range Plan for Dealing All BWRs NA with Stress Corrosion Cracking in BWR Piping 93 (B098) Steam Binding of Auxiliary All PWRs L-88-237, dated Feedwater Pumps May 24, 1988 99 (L817) RCS/RHR Suction Line Valve All PWRs Notes 4, 5 Interlock on PWRs 124 Auxiliary Feedwater System AN0-1&2, Rancho NA Reliability Seco, Prairie Island 1&2, Crystal River-3 Ft. Calhoun-A-13 (B017) Snubber Operability Assurance- All Plants NA See 8022 Hydraulic Snubbers Hydraulic snubbers have been replaced with mechanical snubbers

5

~GSI MPA ~No. TITLE APPLICABILITY STATUS* t'OMMENTS A-13 (B022) Snubber Operability Assurance All Plants Amend 90, dated Mechanical Snubbers Oct 14, 1983 A-16 (D012) Steam Effects on BWR Core Oyster Creek NA Spray Distribution & NMP-1 A-35 (B023) Adequacy of Offsite Power All Plants Amend 98, dated Systems Aug 14, 1984 B-10 Behavior of BWR Mark III All BWR Mark III NA Containments Plants B-36 Develop Design, Testing and All Plants with NA Maintenance Criteria for OL Applications Atmosphere Cleanup System After 4/1/80 Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Uentilation Systems B-63 (B045) Isolation of Low Pressure All Plants Order dated Systems Connected to the Reactor April 20, 1981 Coolant System Pressure L-87-264, dated Boundary 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. 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.

3 ~ 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.

4 ~ 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.

5. The NRC has not yet completed its review of this item.

~Pi

~ m ENCLOSURE 2 FACILITY NAME: Turke Point Unit 4 DOCKET NO.: - 1 ilCENSEE: ht C GSI Status Summar Licensee Staff GSI/MPA Status Status No. Title Determination Determination Remarks 40 (B065) Safety Concerns N/A N/A Associated With Pipe Breaks In The BWR Scram System 41 (B058) BWR Scram Discharge N/A N/A Volume Systems 43 (8107) Reliability Of Licensee met requirements of Air Systems GL 88-14 by letter dated 5/30/90.

Licensee still implementing identified improvements. Expect to complete by 12/07/90.

51 (L913) Improving the Licensee response dated 1/30/90 Reliability of established the required 5 Open-Cycle Servi ce programs. All additional actions Water Systems 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 I/12-90 I/12-90 RG 1.97 implementation inspected Monitoring in IR 90-01 and found acceptable.

Area Rad. Monitoring System upgrade to be complete 12/31/90.

Exception for ARMS had been re-quested to permit a range ~f 10 3 to 10 R/hr instead of 10 to 10 4 .

Licensee will withdraw request for exception and meet RG 1.97 by 12/31/90.

Licensee Staff GS I/HPA Status Status No. Title Determination Determination Remarks 75** (8076) Item 1.1 - Post-Trip C C 5/31/85 Review (Program Description and Procedure) 75 (B085) Item 1.2 - Post-Trip C 8/15/85 Review - Data and Information Capability 75 (B077) Item 2.1 - Equipment C 4/17/87 Classification and Vendor Interface (Reactor Trip System Components) 75 (B086) Item 2.2.1 - Equipment C 4/17/87 Li censee implementation Classification for complete. Staff issued Saf ety-Re 1 ated SER 8/09/90.

Components 75 (L003) Item 2.2.2 - Vendor E/09-29-90 GL 90-03 supercedes 2.2.2.

Interface for Safety-Related Components 75 (B078) Items 3.1.1 & 3.1.2- C 7/31/86 Post - Maintenance Testing (Reactor Trip System Components)

• • The dates shown for the Salem ATWS items are contained in a 4/5/90 letter from the licensee.

Licensee Staff GSI/MPA Status Status No. Title Determination Determination Remar ks 75 (B079) Item 3.1.3 - Post- C 7/31/86 Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components) 75 (B087) Items 3.2.1 5 3.2.2- I/9-1-90 I/10/15/90 Licensee has indicated verbally Post-Maintenance Testing (All Othe~

Safety-Related item was completed about 9/1/90.

Letter to NRC documenting completion expected by 10/15/90.

~

Components) 75 (B088) Item 3.2.3 - Post- C 7/31/86 SER dated ll/14/85.

Maintenance Testing-Changes to Test Requirements (All Other Safety-Related Components) 75 (B080) Item 4.1 - Reactor C 11/8/83 Trip System Reliability (Vendor-Related Modifications) 0

Licensee Staff GSI/MPA Status Status No. Title Determination Determination Remarks 75 (B081) Items 4.2.1 & 4.2.2- C C 1/18/85 Reactor Trip System Reliability-Maintenance and Testing (Preventative Maintenance and

.Surveillance Program for Reactor Trip Breakers) 75 (8082) Item 4.3 - Reactor Trip C 6/30/86 System Reliability-Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B090) Item 4.3 - Reactor Trip C 12/31/87 Licensee's design accepted by System Reliability- NRC. TS are part of the TS Tech Spec Changes upgrade amendment issued 8/28/90.

(Automatic Actuation of Implementation required by 8/28/91.

Shunt Trip Attachment TS have been implemented in 1987 For Westinghouse and by administrative procedure.

B&W Plants) 75 (B091) Item 4.4 - Reactor Trip N/A N/A System Reliability

( Improvements in Maintenance and Test Procedures for B&W Plants)

Licensee Staff GSI/HPA Status Status No. Ti tie Determination Determination Remarks 75 (B092) Item 4.5.1 - Reactor C 5/1/86 Trip System i i 1 i ty-Diverse Re 1 ab Trip Features (System Functional Testing) 75 (B093) Items 4.5.2 8 4.5.3- C 5/1/86 Reactor Trip System Reliability-Test Alternatives and Intervals (System Functional Testing) 86 (B084) Long Range Plan for N/A N/A Dealing with Stress Corrosion Cracking in BWR Piping 93 (B098) Steam Binding of C 5/24/88 NRC letter dated 6/15/88.

Auxiliary Feedwater Pumps 99 (L817) RCS/RHR Suction I 12/91 GL 88-17, Licensee actions/

Line Valve schedules provided in letters Interlock on PWRs dated 1/3/89, 2/1/89. Staff review not complete. Imple-mentation expected to be complete 12/91.

124 Auxiliary Feedwater N/A N/A-System Rel iabi 1 ity A-13 (B017) Snubber Operability N/A N/A Assurance-Hydraulic Snubbers

Licensee Staff GSI/MPA Status Status No. Tit1e Determination Determination Remarks A-13 (B022) Snubber Operability C 10/14/83 Amendments 96 and 90 for Assurance - Mechanical Units 3 and 4 Snubbers A-16 (D012) Steam Effects on BWR N/A N/A Core Spray Distribution A-35 (8023) Adequacy of Offsite C 5/10/84 Licensee (G. Salamon) indicated Power Systems 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."

B-10 Behavior of BWR N/A N/A Hark III Containments B-36 Develop Design, N/A N/A Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems

Licensee Staff GSI/HPA Status Status No. Title Determination Determination Remarks B-63 (B045) Isolation of Low C 4/20/81 Pressure Systems Connected to the Reactor Coolant System Pressure Boundary

Item Status 99 (L817) RCS/RHR Suction Line Valve Interlock on PWRs (cont)

(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

~Li 4

ENCLOSURE 2 FACILITY NAME: Turke Point Unit 4

=DOCKET NO.: - 1 LICENEEE: ht C GSI Status Summar Licensee Staff GSI/MPA Status Status No. Ti tie Determination Determination Remarks 40 (B065) Safety Concerns N/A N/A Associated With Pipe Breaks In The BWR Scram System 41 (B058) BWR Scram Discharge N/A N/A Volume Systems 43 (B107) Reliability Of Li censee met requirements of Air Systems GL 88-14 by letter dated 5/30/90.

Licensee still implementing identified improvements. Expect to complete by 12/07/90.

51 (L913) Improving the Licensee response dated 1/30/90 Reliability of established the required 5 Open-Cycle Service programs. All additional actions Water Systems 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 I/12-90 I/12-90 RG 1.97 implementation inspected Monitoring in IR 90-01 and found acceptable.

Area Rad. Monitoring System upgrade to be complete 12/31/90.

Exception for ARMS had been re-quested to permit a range ~f 10 3 to 10 R/hr instead of 10 to 10 .

Licensee will withdraw request for exception and meet RG 1.97 by 12/31/90.

~

Cc ~ iU~ $ QA pe l'3 J

~ )hi I *

.~" s ~ avVI ~ BC*=

,>'..'3~ " L~ (i". 4 k'~'

~"~~i~+" r s~ ada u .

4L G ( ~ ic yv<

vflU'q ~CCGC+~

v4 3 U2i)GC,.

<<4 ~ ~~ y ~ La=~~

i)) yV J V CUAk v vlaa ~

-*=I OLOOLnU2 ' cL.

...2 OL 3."2LGCglOUc,

' ~<+=

~~Gild LvQ

~a" ~ -

C",

~ J 'i 4 4 s v =-

8 QELlk EGG

~L A'Li6."~"O'X'." .

l .Lg ..~~a@~

. - eCGL 0~46q "b'av .

LGdfl Ji GLI>U~2 O.

,t,( ~

'f.li. - i.c., i, il 4 i 44L k4 CI Q* = jic pcc

~ 11~i I *

~ ~

Licensee Staff GSI/NPA Status Status No. Title Determination Determination Remarks 75** (B076) Item 1.1 - Post-Trip C C 5/31/85 Review (Program Description and Procedure) 75 (8085) Item 1.2 - Post-Trip C 8/15/85 Review - Data and Information Capability 75 (B077) Item 2.1 - Equipment C 4/17/87 Classification and Vendor Interface (Reactor Trip System Components) 75 (B086) Item 2.2.1 - Equipment C 4/17/87 Licensee implementation Classification for complete. Staff issued Saf ety-Related SER 8/09/90.

Components 75 (L003) Item 2.2.2 - Vendor E/09-29-90 GL 90-03 supercedes 2.2.2.

Interface for Saf ety-Related Components 75 (B078) Items 3.1.1 5 3.1.2- '

7/31/86 Post - Maintenance Testing (Reactor Trip System Components)

• • The dates shown for the Salem ATMS items are contained in a 4/5/90 letter from the licensee.

Licensee Staff GSI/MPA Status Status No. Title Determination Determination Remar ks 75 (8079) Item 3.1.3 - Post- C 7/31/86 Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components) 75 (B087) Items 3.2.1 In 3.2.2- I/9-1-90 I/10/15/90 Licensee has indicated verbally Post-Maintenance item was completed about 9/1/90.

Testing (All Other Letter to NRC documenting Safety-Related completion expected by 10/15/90.

Components) 75 (B088) Item 3.2.3 - Post- C 7/31/86 SER dated ll/14/85.

Maintenance Testing-Changes to Test Requirements (All Other Safety-Related Components) 75 (B080) Item 4.1 - Reactor C 11/8/83 Trip System Reliability (Vendor-Related Modifications)

-Licensee Staff GSI/I'IPA Status Status No. Title Determination Determination Remarks 75 (B081) Items 4.2.1 & 4.2.2- C 1/18/85 Reactor Trip System Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (B082) Item 4.3 - Reactor Trip C 6/30/86 System Reliability-Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B090) Item 4.3 - Reactor Trip C 12/31/87 Licensee's design accepted by System Reliability- NRC. TS are part of the TS Tech Spec Changes upgrade amendment issued 8/28/90.

(Automatic Actuation of Implementation required by 8/28/91.

Shunt Trip Attachment TS have been implemented in 1987 For Westinghouse and by administrative procedure.

B&H Plants) 75 (B091) Item 4.4 - Reactor Trip N/A N/A System Reliability (Improvements in Maintenance and Test Procedures for B&W Plants)

Licensee Staff GSI/NPA Status Status No. Title Determination Determination Remarks 75 (8092) Item 4.5.1 - Reactor C 5/1/86 Trip System Reliability-Diverse Trip Features (System Functional Testing) 75 (B093) Items 4.5.2 5 4.5.3- C 5/1/86 Reactor Trip System Reliability-Test Alternatives and Intervals (System Functional Testing) 86 (B084) Long Range Plan for N/A N/A Dealing with Stress Corrosion Cracking in BWR Piping 93 (B098) Steam Binding of C 5/24/88 NRC letter dated 6/15/88.

Auxiliary Feedwater Pumps 99 (L817) RCS/RHR Suction I 12/91 GL 88-17, Licensee actions/

Line Valve schedules provided in letters Interlock on PWRs dated 1/3/89, 2/1/89. Staff review not complete. Imple-mentation expected to be complete 12/91.

124 Auxiliary Feedwater N/A N/A System Reliability A-13 (B017) Snubber Operability N/A N/A Assurance-Hydraulic Snubbers

P

~

Vg Licensee Staff GSI/MPA Status Status No. Title Determination Determination Remarks A-13 (B022) Snubber Operability C 10/14/83 Amendments 96 and 90 for Assurance - Mechanical Units 3 and 4 Snubbers A-16 (D012) Steam Effects on BWR N/A N/A Core Spray Distribution A-35 (B023) Adequacy of Offsite C 5/10/84 Licensee (G. Salamon) indicated Power Systems 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."

B-10 Behavior of BWR N/A N/A Mark III Containments B-36 Develop Design, N/A N/A Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems

Licensee Staff GSI/MPA Status Status No. Title Determination Determination Remarks B-63 (B045) Isolation of Low C C 4/20/81 Pressure Systems Connected to the Reactor Coolant System Pressure Boundary

Item Status 99 (L817) RCS/RHR Suction Line-Valve-Interlock-on-PWRs (cont)

(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.

Original signed by Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects I/II

Enclosures:

As stated

~g DISTRIBUTION GEdison DMi 1 1 er RSchol1 OFC :PN:PDII-2 )~+:0:PDII-2 W WWW WW ~ 0 NAME :GEdison :HBe DATE :/ /9/ /90  : P )

/90 OFFICIAL RECORD COPY Document Name: MEMO GSI TURKEY 4

pe AEQ(g Wp 0 UNITED STATES ss s 1~

NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555

/y ss October 1, 1990

++*<<>>

Docket No. 50-251 MEMORANDUM FOR: Docket File FROM: Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects - I/II

SUBJECT:

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) 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.

• 51 (L913) 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 Status 67.3.3 (A017) 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.

75 (L003) 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.

75 (B087) 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.

99 (L817) 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 Status 99 (L817) RCS/RMR Suction Line Valve Interlock on PMRs (cont)

(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.

Original signed by Gordon E. Edison, Sr. Project Manager Project Directorate II-2 Division of Reactor Projects I/II

Enclosures:

As stated

~g DISTRIBUTION GEdison DMiller RScholl OFC:PN:PDII-2 )~+:0:PDII-2 W W ~ WW WW NAME :GEdison :HBe we ~

DATE :g /9/ /90  : KP t /90 OFFICIAL RECORD COPY Document Name: MEMO GSI TURKEY 4