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 
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:""""*'

33 1

>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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i cci-Gerald Charnoff, Esq..

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

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Missouri Public Service Commission:

P.O.

Box 360 Jefferson City, MO 65102 1

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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)

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Attcchment'

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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 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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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-

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(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-

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Maintenance Testing (Reactor. Trip

' 7/3/85; UIRRC-687.

System Components)

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

~(3/12/64).

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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).

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Attcchment 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.

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 '

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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,

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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

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A-35 (B023)

' Adequacy of Offsite Power Systems-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 i _

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B-36

-Develop Design, Testing and with OL~Ap-EMaintenance Criteria'for~ Atmosphere-

' Cleanup System Air Filtration and plicationsJ

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' After'.4/1/80

-Safety Features Systems'ead for-1,

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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 ts.

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ULNRC -2235 Pago 7 of 7 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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