ML20043C195
| ML20043C195 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/30/1990 |
| From: | Wallace E TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-90-04, GL-90-4, NUDOCS 9006040215 | |
| Download: ML20043C195 (23) | |
Text
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' TENNESSEE VALLEY AUTHORITY CH ATTANOOG A, TENNESSEE 37401 -
l SN 1578 Lookout Place MAY 301980 U.S. Nuclear Regulatory Commission-ATTN:
Document Control Desk Washington, D.C.
20555 Gentlemen:
In the Matter of.
)
Docket Nos. 50-259-Tennessee Valley Authority
)
50-260 50-296 t
BROWNS FERRY NUCLEAR PLANT.(BFN) - STATUS OF IMPLEMENTATION OF GENERIC SAFETY ISSUES (GENERIC LETTER 90-04)
This letter provides:TVA's-response to Generic letter 90-04, Request for Information on the Status of Licensee Implementation of Generic Safety Issues (GSIs) Resolved with Imposition of Requirements or Corrective-Actions, for BFN.
Enclosure i provides the status of GSIs for BFN Unit 1.
provides the status of GSIs for BfN Unit 2. provides the status of.GSIs for BFN Unit 3.
This: letter does not include new commitments.. Forecast implementation dates provided for GSIs reflect previous correspondence and anticipated restart dates.
If you have any questions, please telephone Patrick P. Carter, Manager of Site Licensing, at (205) 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY f
)
- llace, nfge'r E. G.
a Nuclear Licensing and Regulatory Affairs Enclosures cc:
See page 2
$b!$bk
[
P An Equal Opportunity Employer
3
+
U.S. Nuclear Regulatory Commission MM 301990 cc (Enclosures):
Ms S. C. Black, Assistant Director for Projects TVA Projects Division U.S. Nuclear Regulatory Commission One White Flint, North 11555-Rockville Pike Rockville, Maryland 20852 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. B. A. Wilson, Assistant Director for Inspection Programs TVA Projects Division U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 l
M ENCLOSURE 1 STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 1 GSI/
TITLE APPLICABILITY STATUS COMMENTS-(MPA No.1 40 Safety Concerns Associated with All BWRs Complete Completion based upon issuance (B065)
Pipe Breaks in the BWR Scram 1/3/86 of Generic Letter (GL) 86-Oli dated January 3, 1986.
System Implementation of visual verification assumption contained in the GL was never requested by the Staff and is not currently required by the ASME code.
41 BWR Scram Discharge Volume All BWRs Complete Completion of the 6/27/84 June 24, 1983 Order is (B058)
Systems certified by TVA letter, dated June 27, 1984.
43 Reliability of Air Systems All Plants Implementing TVA's response to GL 88-14 was 1/95 submitted by letter dated (B107)
February 23, 1989.
51 Improving the Reliability of All Plants Implementing -TVA's response to GL 89-13 was-(L913)
Open-cycle Service Water Systerca 1/93 submitted by letter dated Farch 16, 1990.
67.3.3 Improved Accident Monitoring All Plants
' Implementing Implementation with the 1/95 exception of qualified neutron (A017) monitoring instrumentation.
Refer to BWR Owners' Group February 21, 1990 letter (BWROG-9025).
75 Generic Letter 83-28, Item 1.1 -
All Plants Complete Completion based upon NRC (B076)
Post-Trip Review (Program 6/17/85 Safety Evaluation, dated June 17, 1985, which stated I
Description and Procedure) the program and procedures were acceptable.
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Page 2 of'7 ENCLOSURE 1 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 1 GSI/
TITLE APPLICABILITY STATUS COMMENTS fMPA No.)
75 Generic Letter 83-28, Item 1.2 -
All Plants Implementing Completion of item requires (B085)
Post-Trip Review - Data and 1/95 installation of upgraded Information Capability process computer. ' Reference NRC's June 12, 1985 Safety Evaluation.
75 Generic Letter 83-28, Item 2.1 -
All Plants Complete Completion based upon NRC (B077)
Equipment Classification and 5/1/89 Safety Evaluations, dated Vendor Interface (Reactor Trip September 2, 1986 (Item 2.1, Part 1) and May 1, 1989 System components)
(Item 2.1, Part 2).
TVA's
-responses were found to be acceptable.
75 Generic Letter 83-28, All Plants Complete Completion based upon NRC (B086)
Item 2.2,1 - Equipment 6/1/89 Safety Evaluation, dated June 1, 1989, which states Classification for Safety
-TVA's response was acceptable.
Related Components 75 Generic Letter 83-28, Item 2.2.2 All Plants Under The NRC issued a revised-(LOO 3)
- Vendor Interface for Safety Evaluation position on this item in GL 90-03, dated March 20, Related Componente 1990.
TVA's response is required by September 25, 1990.
75 Generic Letter 83-28, All Plants Complete TVA's commitments are (B078)
Items 3.1.1 and 3.1.2 - Post-8/15/88 reflected in the NRC's March 23, 1988 Safety Maintenance Testing (Reactor Evaluation.- These comunitments Trip System Components) were completed July 29,,1988 (Item 3.1.1) and August 15, 1988 (Item 3.1.2).
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Page 3 of-7 ENCLOSURE 1 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 1 GSI/
. TITLE
' APPLICABILITY STATUS COMMENTS (MPA No.)
75 Generic Letter 83-28, Item 3.1.3 All Plants Complete Completion based upon NRC (BO79)
- Post-Maintenance Testing -
10/27/86 Safety Evaluation, dated October 27, 1986, which states Changes to Test Requirements TVA's response was acceptable.
(Reactor Trip System Components) 75 Generic Letter 83-28, All Plants Complete Completion based upon NRC (B087)
Items 3.2.1 and 3.2.2 - Post-3/23/88
. Safety Evaluation, dated March 23, 1988, which states Maintenance Testing (All other TVA's programs are acceptable.
Safety Related Components) 75 Generic Letter 83-28, Item 3.2.3 All Plants Complete Completion based upon NRC (B088)
- Post-Maintenance Testing -
10/27/86 Safety Evaluation, dated October 27, 1986, which states Changes to Test Requirements TVA's response was acceptable.
(All Other Safety Related Components) 75 Generic Letter 83-28, Item 4.1 -
All Plants Not The applicability section for (B080)
Reactor Trip System Reliability Applicable this item in GL 83-28 states:
"This action applies to all (Vendor Related Modifications)
PWR licensees and OL applicants."
75 Generic Letter 83-28, All PWRs Not BFN is a BWR (B081)
Items 4.2.1 and 4.2.2 - Reactor Applicable Trip System Reliability -
Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
Page 4 of 7 ENCLOSURE 1 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS-FERRY NUCLEAR PLANT (BFN) - UNIT 1 GSI/
TITLE APPLICABILITY STATUS COMMENTS (MPA No.)
75 Generic Letter 83-28, Item 4.3 -
All W and B&W Not BFN is a BWR (B082)
Reactor Trip System Plants Applicable Reliability - Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 Generic Letter 83-28, Item 4.3 -
All W and B&W Not BFN is a BWR (B090)
Reactor Trip System Plants Applicable Reliability - Tech. Spec.
Changes (Automatic hetuation of Shunt' Trip Attachment for Westinghouse and B&W Plants) 75 Generic Letter 83-28, Item 4.4 -
All B&W Plants Not BFN is a BWR (B091)
Reactor Trip System Reliability Applicable (Improvements in Maintenance and Test Procedures for B&W Plants) 75 Generic Letter 83-28, Item 4.5.1 All Plants Complete Completion based upon NRC (B092)
- Reactor Trip System 4/14/86 Safety Evaluation, dated Reliability - Diverse Trip April 14, 1986, which states Features (System Functional TVA's response was acceptable.
Testing) 75 Generic Letter 83-28, All Plants Under Item 4.5.2 is considered (B093)
Items 4.5.2 and 4.5.3 - Reactor Evaluation complete based upon NRC Safety Trip System Reliability - Test 1/95 Evaluation, dated September 2, Alternatives and Intervals 1986, which states TVA's response was acceptable.
(System Functional' Testing)
Closure of Item 4.5.3 requires review ~for conformance to BWROG approved analysis.
Page 5 of 7 ENCLOSURE 1 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 1 GSI/
TITLE APPLICABILITY STATUS COMMENTS (MPA No.)
86 Inng Range Plan for Dealing with All BWRs Completed Completion based upon issuance.
(B084)
Stress Corrosion Cracking in BWR 1/25/88 of GL 88-01, dated January 25, 1988, which superseded Piping
.GL 84-11.
Actions resulting from GL 88-01 are tracked under USI A-42 (NPA B-05).
93 Steam Binding of Auxiliary All PWRs Not BFN is a BWR (B098)
Feedwater Pumps Applicable 99 RCS/RHR Suction Line Valve All PWRs Not BFN is a BWR (L817)
Interlock on PWRs Applicable 124 Auxiliary Feedwater System ANO-1&2, Rancho Not BFN is not listed Reliability Seco, Prairie Applicable Island IE2, Crystal River-3 Ft. Calhoun A-13 Snubber Operability Assurance -
All Plants Complete Completion based upon issuance (B017)
Hydraulic Snubbers 5/24/82 of Technical Specification Amendment No. 84, dated May 24, 1982, which stated that the requirements of the Staff's November 20, 1981-Generic Letter are incorporated.
1.
Page 6 of 7 ENCLOSURE 1 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 1 GSI/
TITLE APPLICABILITY STATUS COMMENTS (MPA No.)
A-13 Snubber Operability Assurance -
All Plants Complete Completion based'upon issuance (B022)
Mechanical Snubbers S/24/82 of Technical Specification Amendment No. 84, dated May 24, 1982, which stated that the requirements of the Staff's November 20, 1981 Generic Letter are incorporated.
A-16 Steam Effects on BWR Core Spray Oyster Creek &
Not BFN is not listed (D-012)
Distribution NMP-1 Applicable A-35 Adequacy of Offsite Power All Plants Complete Modifications are reflected in 1981 Technical Specification (B023)
Systems Amendment No.'75, dated September 3, 1981.
B-10 Behavior of BWR Mark-III All BWR Not BFN has a Mark I containment.
Containments Mark III Plants Applicable B-36 Develop Design, Testing and All Plants with Not BFN docketed its OL Maintenance Criteria for OL Applications Applicable application on September 25, Atmosphere Cleanup System Air After 4/1/80 1970.
Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems 1
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.Mm ENCLOSURE 2 STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 GSI/
TITLE APPLICABILITY STATUS COMMENTS iMPA No.)
40 Safety Concerns Associated with All BWRs Complete Completion based upon-issuance (B065)
Pipe Breaks in the BWR Scram 1/3/86 of Generic Letter (GL) 86-01, dated January 3,-1986.
System Implementation of visual verification assumption contained in the GL was never-requested by the Staff and is not currently required by the ASME code.
41 BWR Scram Discharge Volume All BWRs Complete Modifications described in TVA 12/11/88 letter, dated' June 27, 1984.
(B058)
Systems 43 Reliability of Air Systems All Plants Implementing TVA's response to GL 68-14 was 9/90 submitted by letter dated (B107)
February 23, 1989.
51 Improving the Reliability of All Plants Implementing TVA's response to GL 89-13 was (L913)
Open-Cycle Service Water Systems 1/93 submitted by letter dated March 16, 1990.
67.3.3 Improved Accident Monitoring All Plants Implementing Implementation with the 9/92 exception of qualified neutron (A017) monitoring instrumentation.
Refer to BWR Owners' Group February 21, 1990 letter (BWROG-9025).
75 Generic Letter 83-28, Item 1.1 -
All Plants Complete Completion based upon NRC (BO76)
Post-Trip Review-(Program 6/17/85 Safety-Evaluation, dated June 17, 1985, which stated Description and Procedure) the program and procedures were acceptable.
M_-
._.m Page 2 of 7-
' ENCLOSURE 2 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 GSI/
TITLE APPLICABILITY
' STATUS.
COMMENTS' (MPA No.)
75 Generic Letter 83-28, Item 1.2 -
All Plants Implementing Completion of item requires (B085)
Post-Trip Review - Data and 9/92 installation of upgraded Information capability process computer. Reference..
NRC's June 12, 1985 Safety.
~ Evaluation.
75 Generic Letter 83-28, Item 2.1 -
All~ Plants Complete' Completion based upon NRC (B077)
Equipment Classification and 5/1/89 Safety Evaluations, dated Vendor Interface (Reactor Trip September 2, 1986 (Item 2.1, Part 1) and May 1, 1989 System Components)
(Item 2.1, Part 2).
TVA's responses were found to be acceptable.
75 Generic Letter 83-28, All Plants Complete Completion based upon NRC (B086)
Item 2.2.1 - Equipment 6/1/89 Safety Evaluation, dated June 1, 1989, which states Classification for Safety TVA's response was acceptable.
Related Components 75 Generic Letter 83-28, Item 2.2.2 All Plants Under The NRC issued a revised (LOO 3)
- Vendor Interface for Safety Evaluation position on this item in.
GL 90-03, dated March 20, Related Components 1990.
TVA's response is required by September 25, 1990.
75 Generic Letter 83-28, All Plants Complete TVA's commitments are (B078)
Items 3.1.1 and 3.1.2 - Post-8/15/88 reflected in the NRC's March 23, 1988 Safety Maintenance Testing (Reactor Evaluation. These commitments Trip System Components) were completed July 29, 1988 (Item 3.1.1) and August-15, 1988 (Item 3.1.2)..
~ ~.
Page 3 of'7 ENCLOSURE 2 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 GSI/
TITLE APPLICABILITY STATUS COMMENTS fMPA No.)
75 Generic Letter 83-28, Item 3.1.3 All Plants Complete Completion based upon NRC (B079)
- Post-Maintenance Testing -
10/27/86 Safety Evaluation, dated October 27, 1986, which states Changes to Test Requirements TVA's response was acceptable.
(Reactor Trip System Components) 75 Generic Letter 83-28, All Plants complete Completion based upon NRC (B087)
Items 3.2.1 and 3.2.2 - Post-3/23/88 Safety Evaluation, dated March 23, 1988, which states Maintenance Testing (All Other TVA's programs are acceptable.
Safety Related Components) 75 Generic Letter 83-28, Item 3.2.3 All Plants Complete Completion based upon NRC (B088)
- Post-Maintenance Testing -
10/27/86 Safety Evaluation, dated October 27, 1986, which states Changes to Test Requirements TVA's response was acceptable.
(All Other Safety Related Components) 75 Generic Letter 83-28, Item 4.1 -
All Plants Not The applicability section for (B080)
Reactor Trip System Reliability Applicable this item in GL 83-28 states:
"This action applies to all (Vendor Related Modifications)
PWR licensees and OL applicants."
75 Generic Letter 83-28, All PWRs Not BFN is a BWR (B081)
Items 4.2.1 and 4.2.2 - Reactor Applicable Trip System Reliability -
Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
4' i,'
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Page 4 of 7.
' ENCLOSURE 2 (Continued)
STATUS OF GENERIC SAFETY ISSUZS BROWNS FERRY NUCLEAR PLANT (BFN) - LMIT 2 l
GSI/
TITLE APPLICABILITY STATUS COMMENTS (MPA No.)
l 75 Generic Letter 83-28, Item 4.3 -
'All W and B&W Not BFN is a BWR l
(BO82)
Reactor Trip System Plants Applicable l.
Reliability - Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 Generic Letter 83-28, Item 4.3 -
All W and B&W Not BFN is a BWR (BO90)
Reactor Trip System Plants Applicable Reliability - Tech. Spec.
Changes (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 Generic Letter 83-28, Item 4.4 -
All B&W Plants Not BFN is a BWR (BO91)
Reactor Trip System Reliability Applicable (Improvements in Maintenance and Test Procedures for B&W Plants) 75 Generic Letter 83-28, Item 4.5.1 All Plants Complete Completion based upon NRC i
(B092)
- Reactor Trip System 4/14/86 Safety Evaluation, dated Reliability - Diverse Trip April 14, 1986, which states l
Features (System Functional TVA's response was acceptable.
Testing) 75 Generic Letter 83-28, All Plants Under Item 4.5.2 is considered (BO93)
Items 4.5.2 and 4.5.3 - Reactor Evaluation complete based upon NRC Safety Trip System Reliability - Test 9/90 Evaluation, dated September 2, Alternatives and Intervals 1986, which states TVA's (System Functional Testing) response was acceptable. BFN is reviewing Item 4.5.3-for conformance to BWROG approved-analysis.
~
Page 5 of 7-ENCLOSURE 2 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 2 GSI/
TITLE APPLICABILITY STATUS COMMENTS (MPA No.)
86 Long Range Plan for Dealing with All BWRs completed Completion based upon issuance (B084)
Stress Corrosion Cracking in BWR 1/25/88 of GL 88-01, dated January 25, 1988, which superseded Piping GL 84-11.
Actions resulting from GL 88-01 are tracked under USI A-42-(MPA B-05).
93 Steam Binding of Auxiliary All PWRs Not BFN is a BWR (B098)
Feedwater Pumps Applicable 99 RCS/RHR Suction Line Valve All PWRs Not BFN is a BWR (L817)
Interlock on PWRs Applicable 124 Auxiliary Feedwater System ANO-1&2, Rancho Not BFN is not listed Reliability Seco, Prairie Applicable Island 1&2, Crystal River-3 Ft. Calhoun A-13 Snubber Operability Assurance -
All Plants Complete Completion based upon issuance (B017)
Hydraulic Snubbers 5/24/82 of Technical Specification Amendment No. 81, dated May 24, 1982, which stated that-the requirements of the Staff's November 20, 1981 Generic. Letter are incorporated.
m.
l 2
Page 6.of 7 ENCLOSURE 7 (Continued)
STATUS OF GENERM SAFETY ISSUES BROWNS. FERRY. NUCLEAR PLANT (BFN) - UNIT 2 GSI/
TITLE APPLICABILITY STATUS COMMENTS (MPA No.)
A-13 Snubber Operability Assurance -
All Plants Complete Completion based upon issuance (8022)
Mechanical Snubbers 5/24/82 of Technical Specification Amendment No. 81, dated' May 24, 1982, which stated that the requirements of the Staff's November 20, 1981' Generic Letter are incorporated.
A-16 Steam Effects on BWR Core Spray Oyster Creek &
Not BFN is not listed (D-012)
Distribution NMP-1 Applicable A-35 Adequacy of Offsite Power All Plants complete Modifications are reflected in 1981 Technical Specification (B023)
Systems Amendment No. 72, dated September 3, 1981.
B-10 Behavior of BWR Mark III All BWR Not BFN has a Mark I containment.
Containments Mark III. Plants Applicable B-36 Develop Design, Testing and All Plants with Not BFN docketed its OL Maintenance criteria for OL Applications Applicable application on September 25, Atmosphere Cleanup System Air After 4/1/80 1970.
Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems l
l l
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. p:-
, ~.
Page 7'of.7 ENCLOSURE 2 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY. NUCLEAR PLANT (BFN) - UNIT 2
-GSI/
TITLE APPLICABILITY STATUS COMMENTS (MPA No.)
B-63 Isolation of Low Pressure All Plants Complete Completion based upon NRC (BO45}
Systems Connected to the Reactor 8/8/80 letter to TVA, dated August 8, 1980,'which states the valve coolant System Pressure Boundary configurations discussed in-NRC's February 23, 1980 letter do not exist at BFN.
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ENCIOSURE 3 STATUS OF GENERIC SAFETf ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 GSI/
TITLE APPLICABILITY STATUS COMMENTS (MPA No.1 40 Safety Concerns Associated with All BWRs Complete Completion based upon issuance (B065)
Pipe Breaks in the BWR Scram 1/3/86 of Generic Letter (GL) 86-01, dated January 3, 1986.
System Implementation of visual verification assumption contained in the GL was never requested by the Staff and is not currently required by the ASME code.
41 BWR Scram Discharge Volume All BWRs Implementing Modifications described in TVA (B058)
Systems 1/93 letter, dated June 27, 1984.
43 Reliability of Air Systems All Plants Implementing TVA's response to GL 88-14 was 1/93 submitted by letter dated (B107)
February 23, 1989.
51 Improving the Rella*>ility of All Plants Implementing TVA's response to GL 89-13 was (L913)
Open-Cycle Service Water Systems 1/93 submitted by letter dated March 16, 1990.
67.3.3 Improved Accident Monitoring All Plants Implementing Impl3:hentatiott with the 1/93 exception of q:2alified naatron (AOl7) moreEtericg inetrumentat8on.
Refer to WKR caeners' Grwp February 21, 1990 letter
( BEGOG-90*,5 ).
75 Generic Letter 83-211, Item 1.1 -
All Plants Complete Completion baned upon NRC (B076)
Post-Trip Review (Program 6/17/85 Safety Evaluation,. dated June 17, 1985, which stated Description and Procedure) the pWram aM procedures sere acceptable.
I ygg
t Page 2 of 7 ENCLOSURE 3 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 GSI/
TITLE APPLICABILITY STATUS COMMENTS fMPA No.)
75 Generic Letter 83-28, Item 1.2 -
All Plants Implementing Completion of item requires (BO85)
Post-Trip Review - Data and 1/93 installation of upgraded Information capability process computer. Reference NRC's June 12, 1965 Safety Evaluation.
75 Generic Letter 83-28, Item 2.1 -
All Plants Complete Completion based upon NRC (BO77)
Equipment Classification and 5/1/89 Safety Evaluations, dated Vendor Interface (Reactor Trip September 2, 1986 (Item 2.1, System Components)
Part 1) and May 1, 1989 (Item 2.1, Part 2).
TVA's responses were found to be acceptable.
75 Generic Letter 83-28, All Plants Complete Completion based upon NRC (BO86)
Item 2.2.1 - Equipment 6/1/89 Safety Evaluation, dated Classification for Safety June 1, 1989, which states Related Components TVA's response was acceptable.
'75 Generic Letter 83-28, Item 2.2.2 All Plants Under The NRC issued a revised (LOO 3)
- Vendor Interface for Safety Evaluation position on this item in Related Components GL 90-03, dated March 20, 1990.
TVA's response is required by September 25, 1990.
J 75 Generic Letter 83-28, All Plants Complete TVA's conealtments are (BO78)
Items 3.1.1 and 3.1.2 - Post-8/15/88 reflected in the NRC's Maintenance Testing (Reactor March 23, 1988 Safety Trip System Components)
Evaluation. These commitments were completed July 29, 1988 (Item 3.1.1) and August 15, 1988 (Ites 3.1.2).
J
Page 3 of 7 ENCLOSURE 3 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 GSI/
TITLE APPLICABILITY STATUS QMEENTS fMPA No.1 75 Generic Letter 83-28, Item 3.1.3 All Plants Complete Completion based upon NRC (8079)
- Post-Maintenance Testing -
10/27/86 Safety Evaluation, dated Changes to Test Requirements October 27, 1986, which states (Reactor Trip System Components)
TVA's response was acceptable.
i 75 Generic Letter 83-28, All Plants Complete Completion based upon NRC (B087)
Items 3.2.1 and 3.2.2 - Post-3/23/88 Safety Evaluation, dated Maintenance Testing (All Other March 23, 1988, wnich states e
Safety Related components}
TVA's programs are acceptable.
75 Generic Letter 83-28, Item 3.2.3 All Plants Complete Completion based upon NRC (B088)
- Post-Maintenance Testing -
10/27/86 Safety Evaluation, dated Changes to Test Requirements October 27, 1986, which states (All Other Safety Related TVA's response was acceptable.
Components) 75 Generic Letter 83-28, Item 4.1 -
All Plants Not the applicability section for (B080)
Reactor Trip System Reliability Applicable this itse in GL 83-28 states (Vendor Related Modifications)
"This action applies to all PWR licensees and OL applicants."
75 Generic Letter 83-28, All PWRs Not BFh is a BWR (BO81)
Items 4.2.1 and 4.2.2 - Reactor Applicable Trip System Reliability -
Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers)
w Page 4 of 7 ENCLOSURE 3 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 GSI/
TITLE APPLICABILITY STATUS SWEENTS (MPA No.1 75 Generic Letter 83-28, Item 4.3 -
All W and B&W Not BFN is a BWR (BO82)
Reactor Trip System Plants Applicable Reliability - Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 Generic Letter 83-28, Item 4.3 -
All W and B&W Not BFN is a BWK (B090)
Reactor Trip System Plants Applicable Reliability - Tech. Spec.
Changes (Automatic Actuatien of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 Generic Letter 83-28, Item 4.4 -
All B&W Plants Not BFN is a BWR (BO91)
Reactor Trip System Reliability Applicable (Improvements in Maintenance and Test Procedures for B&W Plants) 75 Generic Letter 83-28, Item 4.5.'.
All Plants Complete Completion based upon NRC l
(B092)
- Reactor Trip System 4/14/86 Safety Evaluation, dated l
Reliability - Diverse Trip April 14, 1986, which states Features (System Functional TVA's response was acceptable.
Testing) 75
' Generic Letter 83-28, All Plants Under.
Item 4.5.2 is considered (BO93)
Items 4.5.2 and 4.5.3 - Reactor Evaluation complete based upon NRC Safety Trip Syst;em Reliability - Test 1/93 Evaluation, dated September 2, AlternatLves and Intervals 1986, which states TVA's (System Eunctionel Testir.g) response was acceptable.
Closure of Item 4.5.3 requires review for conformance to l
BWROG ayysu d analysis.
I i
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Page 5 of 7 ENCLOSURE 3 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 GSI/
TITLE APPLICABILITY STATUS CoeWENTS iMPA No.1 86 Long Range Plan for Dealing with All BWRs Completed Completion based upon issuance (B084)
Stress Corrosion Cracking in BWR 1/25/88 of GL 88-01, dated January 25, Piping 1988, which superseded GL 84-11.
Actions resulting from GL 88-01 are tracked under USI A-42 (MPA B-05).
93 Steam Binding of Auxiliary All PWRs Not BFN is a BWR (B098)
Feedwater Pumps Applicable 99 RCS/RHR Suction Line Valve All PWRs Not BFN is a BWR (L817)
Interlock on PWRs Applicable 124 Auxiliary Feedwater System ANO-1&2, Rancho Not BFN is not listed Reliability Seco, Prairie Applicable Island 152, Crystal River-3 Ft. Calhoun A-13 Snubber Operability Assurance -
All Plants Corsplete Completion based upon issuance (B017)
Hydraulic Snubbers 5/24/82 of Technical Specification Amendment No. 55, dated May 24, 1982, which stated that the requirements of the Staff's November 20, 1981 Generic Letter are irsc rated.
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2 Page 6 of 7 ENCLOSURE 3 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 CSI/
TITLE APPLICABILITY STATUS COMMENTS
-(MPA No.)
A-13 Snubber Operability Assurance -
All Plants Complete Completion based upon losuance (B022)
Mechanical Snubbers 5/24/82 of Technical Specification Asnendment No. 55, dated May 24, 1982, which stated that the requirements of the Staff's Noveseber 20, 1981 Generic Letter are incorporated.
A-16 Steam Effects on BWR Core Spray Oyster Creek &
Not BFN is not listM (D-012)
Distribution NMP-1 Applicable A-35 Adequacy of Of fsite Power All Plants Complete Modifications are reflected in 1982 Technical Specification (B023)
Systems Amendment No. 52, dated March 29, 1982.
B-lO Behavior of BWR Mark III All BWR Not BFN has a Mark I containment.
Containments Mark III Plants Applicable B-36 Develop Design, Testing and All Plants with Not BFN docketed its OL Maintenance criteria for OL Applications Applicable application on September 25, Atmosphere Cleanup System Air After 4/1/80 1970.
Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems
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Page 7 of 7-ENCLOSURE 3 (Continued)
STATUS OF GENERIC SAFETY ISSUES BROWNS FERRY NUCLEAR PLANT (BFN) - UNIT 3 GSI/
TITLE APPLICABILITY STATUS C0fWENTS (MPA No.1 B-63 Isolation of Low Pressure 7.11 Plants Complete Completion based upon NRC (B045)
Systems Connected to the Reactor 8/8/80 letter to TVA, dated August 8, Coolant System Pressure Boundary 1980, which states the valve configurations discussed in NRC's February 23, 1980 letter do not exist at BFN.
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