ML20043H837

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Forwards Response to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issues at Facility
ML20043H837
Person / Time
Site: Callaway Ameren icon.png
Issue date: 06/21/1990
From: Schnell D
UNION ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR GL-83-28, GL-85-09, GL-85-9, GL-88-17, GL-90-03, GL-90-04, GL-90-3, GL-90-4, ULNRC-2235, NUDOCS 9006260502
Download: ML20043H837 (10)
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. i- l901 Gratiot Strsvt ^

, Post Orhce Box 149 . .

. . St. tours. MsssouriC3166

-' : .314 554 2650 q

i M ON aune 21,- 1990 : wmus EuNmc 11:""""*'

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>U.S'l-Nuclear Regulatory Commission ,

ATTN : - Document = Control ~-' Desk I MailLStation' PI-137

--Washington, D.C.- 20555 i

Gentlemen ULNRC-2235

' DOCKET NUMBER _50-483 CALLAWAY PLANT-GENERIC-SAFETY ISSUES STATUS ~ -

Ref.: NRC Generic Letter 90-04 dated April 25, 1990

.[

The referenced generic. letter requested that.-we provide the- implementation' status of each Generic Safety . ~l Issue ~ (GSI); for our f acility. .The attached table utilizes Enclosuroll from- thef generic letter, and is completed = to i show the status for:each GSI for Callaway Plant. Refer-: . i onces.which form the basis for each GSI status are provided.-

under!the " Comments" column. .t If there are any questions'or if additional '

clarification is needed, please contact Dave Shafer of.Omy' ,

L staff.

Very truly yours,

. G 1

1 l Donald F. Schnell?

1 DES /dvd Attachment

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cci- Gerald Charnoff, Esq. . i Shaw, Pittman,.Potts & Trowbridge -; '

2300 N. Street, N.W.

Washington, D.C. 20037 Dr. J. O. Cermak CFA, Inc. .

4 Professional ' Drive (Suite'110) i Gaithersburg,LMD'20879  ;

R fC.' Knop-  ;

Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission <

Region III-799 Roosevelt-Road Glen'Ellyn, Illinois 60137  ;

Bruce Bartlett  !

Callavay Resident Office-U.S.-Neclear Regulatory Commission RR#1 Steedman, ilissouri- 65077 Anthony T. Gody, Jr. .(2)-

, Office of Nuclear Reactor Regulstion U.S. Nuclear Regulatory Commission Mail Stop P-316 7920 Norfolk Avenue -

Bethesda, MD 20014 Manager, Electric. Department Missouri Public Service Commission: [

P.O. Box 360 Jefferson City, MO 65102 1

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-Nuclear Date

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.D. F. Schnell '['

J.-~E. Birk J.'V. Laux M. A. Stiller l' G. L. Randolph R.--J. Irwin <

H. Wuertenbaecher

  • W. R. Campbell A'. C.-Passwater R. P. Wendling D. E..Shafer D. J. Walker (2)

O..Maynard (WCNOC) '

'N. P. Goel (Bechtel) .

T. P. Sharkey NSRB:(Sandra Auston) -

A /60.V/2 ( 90'-C'f)

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ULNRC- 2235 Peg 2 1 of 7'-

FACILITY NAME: Calleway Plant DOCKET NO.: 50-483 LICENSEE: NPF-30 STAWS OF LICENSEE IMPLEMENTATION OF GENERIC ' SAFETY ISSUES RESOLVED WITE IMPOSITION OF REQUIRE.ETS OR CORRECTIVE ACTIONS GSI/(MPA NO.) - TITLE APPLICAEILITY STATUS * ' C01%TS

. 40 (3065) Safety Concerns Associated with' Pipe All_.BWRs NA

~ Breaks'in the BWR Scram System 41 (B058) BWR Scram Discharge Volume Systems All BWRs NA-43 (B107) Reliability of Air Systems All Plants C - NRC letter dated 3/30/89.

ULNRC-1904 (2/3/89).

51 (L913) Improving the Reliability of All Plants I NRC. letter dated 4/13/90.

Open-Cycle. Service Water Systems ULNRC-2146.(1/29/90).

Confirmatory: letter expected'by 12/90.

67.3.3 (A017) Improved Accident Monitoring

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All Plants C NRC letter & SER dated 4/10/85. 'SLNRC-83-0019 (4/15/83), SINRC-84-107 (8/16/84) and UINRC-619 (4/15/63).

75** (B076) Item 1.1 - Post-Trip Review (Program All Plants C NRC letter & SER dated Description and Procedure) .5/7/85. UINRC-763 (3/12/84).

  • Pl ae se 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 AWS events.

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

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-UINRC-2235 Pcgo 2 of 7

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GSI/(MPA NO.). TITLE APPLICABILITY STATUS * - COMMENTS 75 (B085) Item 1.2 - Post-Trip Review - Data All Plants C :NRC letter & SER dated.-

and Information Capability- ~7/24/86. ULNRC-763 (3/12/84) and - 1225- ~

(12/11/85).

75 (LO77) - Item 2.1 - Equipment Classification All Plants C NRC letter & SER dated and Vendor Interface'(Reactor. Trip 7/21/86. .NRC letter & SERF System Components) dated 12/22/86.

.ULNRC-687~(11/18/83),

-763 (3/12/84),

-829 (5/21/84),

1002.(12/27/84),'and-

- 1098 (5/17/85). .

75 (B086) Item 2.2.1 - Equipment Classification- All Plants C- NRC' letter & SER' dated for Safety-Related Components. 4/10/87. UINRC - 687 (11/18/83),

-;763 (3/12/84)

~ 829'(5/21/84),

- 1002 (12/27/84),.

1098 (5/17/85),'and:

- 1435-(1/27/87).

75 (LOO 3) Item.2.2.2.' Vendor Interface'for ~A11' Plants E NRC letter'& SER dated-Safety-Related Components 4/10/87. .ULNRC - 687 (11/18/83),-

-1763 (3/12/84)-

---829-(5/21/84),

- 1002 (12/27/84),

- 1098 (5/17/85), and-

--1435 (1/27/87).

GL-90-03 response'due 9/25/90.

75 (B078) Items 3.1.1.6 3.1.2 - Post.--. All Plants C NRC. letter & SER dated-Maintenance Testing (Reactor. Trip

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' 7/3/85; UIRRC-687.

System Components) (11/18/83)'and -763.

~(3/12/64).

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UIA3t 2035 Pege 3 of 7.. _

GSI/(MPA No.) TITLE APPLICABILITY STATUS

  • COMMEhTS 75 (B079) Item 3.1.3 - Post-Maintenance All Plants C ' NRC letter & SER dated'

- Testing-Changes to Test Requirements 10/7/86. UINRC-687-(Reactor Trip System Components)- (11/18/83)'and -1356.

.(8/12/86).

75 (B087) Items 3.2.1 & 3.2.2 - Post - All Plants C NRC letter & SER dated Maintenance Testing (All'Other 7/3/85. ULNRC-687 Safety-Related Components) (11/18/83)'and'-763 (3/12/84).

75 (B088) Item 3.2.3 - Post-Maintenance All Plants C- .NRC letter & SER dated' Testing-Changes to Test Requirements 10/7/86.1 UINRC-687-(All Other Safety-Related.  :

(11/18/83) and -1356 Components) (8/12/86).

75 (B080) Item 4.1 -' Reactor Trip System. -All Plants -C' NRC letter & SER dated.

Reliability-(Vendor-Related . 7/3/85. ULNRC-687 Modifications)- ~ (11/18/83) and--763!

(3/12/84).

75 (B081) Items.4.2..'I & 4.2.2  : Reactor Trip. All PWRs C i NRC letter & SER dated System Reliability-Maintenance'and- . 10/28/85. UIXRC-68T _

Testing:(Preventatiye Maintenance and (11/18/83), -763(3/12/84),

Surveillance Program for Reactor Trip- - -829 (5/21/84), and -1002

- Breakers)- - (12/27/84).

75 (B082) Item 4.3 ---Reactor Trip System All W & B&W C -NRC letter & SER dated Reliability - Design Modifications Plants (Modifica- 7/18/84. ULNRC-763 (Automatic Actuation'of Shunt' Trip tion) (3/12/84) and~-1002 Attachment-for Westinghouse and B&W . (12/27/84).

Plants)

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ULNRC- 2235 Page 4'of 7 GSI/(MPA NO.) TITLE APPLICABILITY STATJS* COMMENTS ~

75 (B090) Item 4.3 - Reactor Trip System All W & B&W C OL Amendment 19 dated Reliability - Tech Spec Changes Plants (Tech Specs 4/3/87. ULNRC-1031 (Automatic Actuation of Shunt Trip Auto Shunt (1/29/85), ULNRC-1240 Attachment for Westinghouse and B&W Trip) (1/9/86), (GL-85-09 Plants) . response).

C OL Amendment 34 dated (Tech Specs 2/17/88. .ULNRC-1602 Bypass Bkrs) (9/10/87).

75 (B091) Item 4.4 - Reactor Trip System All B&W NA Reliability (Improvements in Plants Maintenance and Test Procedures for B&W Plants) 75 (B092) Item 4.5.1 - Reactor Trip System All Plants C NRC letter'& SER dated.

Reliability-Diverse Trip Features -7/3/85. ULNRC-687 (System Functional Testing) -(11/18/83) and -763 (3/12/84).

75 (B093) Items-.4.5.2 & 4.5.3 -' Reactor Trip All Plants- C

System Reliability Test NRC letter &'SER dated.

Alternatives and Intervals (System' 6/12/89. UIRRC-687 Functional Testing) (11/18/83). OL Amendment.

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17 (9/8/86). ULNRC-1174 (10/16/85).

86 (BOS4) Long Range Plan for. Dealing- with All BWRs NA Stress Corrosion: Cracking in BWR Piping 93 (B098) Steam Binding of Auxiliary Feedwater All PWRs C Pumps NRC letter dated.7/8/88.

IHNRC-1774 (5/12/86).

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ULNRC-2235- .

Pcgi 5 of-7f 7 GSI/(MPA NO.~) TITLE APPLICABILITY STAR'S*- COMMEhTS'

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99 (L817) RCS/RHR Suction Line Valve Interlock ' All Ph'Rs ' I .. NRC letter dated 3/16/89.-

on Pk'Rs (GL 88-17) UIARC-1889. (1/3/89), and

-1900:(2/1/89). A'redun--

dant RV level indication to be:added Refuel 4E (12/90).

.C OL Amendment 42 dated- 3 (Auto Closure'3/27/89. UIJiRC-1889 Interlock)? .(1/6/89)'and--1910-

.(2/10/89). Modifications Lcompleted 3/89.

124 Auxiliary Feedwater System 'ANO - 1 &'2, . - NA , ~

' Reliability Rancho;Seco, ^

Prairie Is-

, -land:1 & 2, Crystal

' River-3, LFt. Calhoun?

A-13 (B017)

Snubber Operability Assurance - .All Plants NC- Priot-to'OL-issuance.

Hydraulic Snubbers Tech Spec 3/4.7.8. -.

2 A-13 (B022) Snubber. Operability Assurance - :All Plants NC Prior to'OL issuance.

Mechanical Snubbers Tech Spec _3/4.7.8.

A-16 (D012)' Steam Effects on BWR Core Spray-  ; Oyster Creek -NA Distribution. & NMP - 1

' Adequacy of Offsite Power Systems-

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A-35 (B023) '

All Plants- NC Prior to OL issuance. SER-and SSER-3,.SectionL6.2 B-10 Behavior of BWR Mark'III Containments All BVR Mark NA III Plants

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B-36 -Develop Design, Testing and .

' All' Plants- NA '

EMaintenance Criteria'for~ Atmosphere- with OL~Ap-

' Cleanup System Air Filtration and .

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-- . -l Adsorption Unitsifor Engineered- ' After'.4/1/80 ~

-Safety Features Systems'ead for- -

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Normal: Ventilation Systess -

a B-63 (B045)~ Isolation of Low Pressere-Systems 'All-Plants NC~ . Prior-to OL: issuance.'

Connected to the' Reactor 1 Coolant; 1 Tech Spec 3/4.4'.'6.2) i:

System Pressure' Boundary

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  • ULNRC -2235 Pago 7 of 7 I Guidance For Completirig Status Column ir)_ Enc _losure l' (1) Provide a separate entry for.each licensed reactor unit. If the information is identical for multiple units, so state.

(2) If a GSI is not applicable to a unit (s), enter "NA".  ;;;

(3) If a GSI is applicable but no changes were necessary to implement the resolution, enter "NC". If the GSI implementation was' completed' prior to issuance of the-operating license, enter "NC", as no post-licensing changes were necessary.

(4) If a GSI is applicable, submittal of information and/or changes were necessary and such submittals were made or changes are complete, ente r C" . ;Also identify the licensee's document (s) to the NRC which certified completion, and the document date(s). ll (5) If a GSI islapplica'ble and changes are necessary but such changes are not yet fully-implemented,: enter "I" and the projected month and year of completion.

Provide a brief enplanation of the, outstanding work in-the " Comments" column.

(6) If implementation guidance for a resolved GSI was issued recently and the. licensee =is still-evaluating the appropriate response, enter "E" and the: projected response date, ,

(7) The " Comments" column may be used'to explain any entry in the " Status" column.

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