ML19332D092

Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Closure Plan for USI A-10 Will Be Submitted in 1990.Response to USI A-47 Re Safety Implications of Control Sys Will Be Submitted in Mar 1990

ML19332D092
Person / Time
Site:	Hatch
Issue date:	11/22/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, HL-840, NUDOCS 8911300006
Download: ML19332D092 (7)

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Georg:a Power Company 1 1,

333 Pedmont Avenue Attanta Geargia 30308i s

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- Telephone 404 526 3195 l

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' M&hng Address 40 inverness Center Parkway

. Post Of!ce Box 1295

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. Barrungham, Nabama 35201 Telephone 205 866 5581 i

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~ W. o. Hairston, Ill son.or vce Prewoont HL-840 u

Nuehar Operatens I

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' November 22, 1989 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Hashington, D.C.

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PLANT HATCH - UNITS 1, 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 RESE0NSE TO GENERIC LETTER 89-21 Gentlemen:

NRC Generic Letter 89-21," Request for Information Concerning Status

- of. -Implementation of Unresolved Safety Issue (USI) Requirements", was issued _ on.0ctober.-19, 1989 to all holders of operating-licenses and construction permits.

The generic letter requested' licensees to provide.

information concerning; the implementation status-of USI requirements for

.which a final-technical resolution has been achieved. The information is requested in -order to assist the NRC staff 'in their review of USI-

-implementation ' status.

In response, a' mark-up of the table of USIs referenced in_ the generic

. letter.is provided as an enclosure.

Supporting documentation is available. for review upon request.

The status' indicated is consistent.

with' the instructions - provided in the generic _ letter.

The attached' notations regarding-status of individual -items are necessarily brief and cannot address all of the details of the more complex items. Taking these constraints into account, the enclosed information is correct to the best "of my_ knowledge.

'If you have any.' questions in this regard, please contact this office.

Sincerely, u).} hAs H. G. Hairston, III JKB/eb

Enclosure:

Unresolved Safety Issues for Which a Final Technical Resolution has been Achievec 0

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(See next page.)

8911300006 891122 l

PDR ADOCK 05000321 F

PDC

' Georgia Power A e

U.S. Nuclear Regulatory Commission November 22, 1989 Page Two c:' Georaia Power-Company Mr. H. C.__ Nix, Ge'eral Manager - Nuclear Plant n

Mr. 'J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS-U.S. Nuclear Regulatory Commission. Hashington. D.C.

Mr. L. P. Crocker, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaion II Mr. S. D. Ebneter, Regional Administrator

.Mr. J. E. Menning, Senior Resident Inspector - Hatch t

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-ENCLOSURE PLANT HATCH - UNITS 1 AND 2

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NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 GENERIC' LETTER 89-21

. UNRESOLVED SAFETY-. ISSUES FOR HHICH A FINAL-1 TECHNICAL RESOLUTION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE REF. DOCLMENT

' APPLICABILITY '

STATUS /DATE*

REMARKS A-1 Hater Hammer

'SECY 84-119 All C/12-80 Nater hammer is addressed

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NUREG-0927, Rev. 1 in licensed operator' NUREG-0993, Rev. I training'

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NUREG-0737 Item I.A'2.3-SRP revisions A-2/

Asymmetric Blowdown NUREG-0609 PHR N/A MPA D-10 Loads on Reactor Primary. GL 84-04, GDC-4 Coolant Systems A-3 Westinghouse Steam NUREG-0844' H-PHR N/A Generator Tube Integrity SECY 86-97 SECY 88-272 GL 85-02 (No Requirements)

A-4 CE Steam Generator NUREG-0844, SECY 86-97 CE-PHR N/A Tube Integrity SECY 88-272 GL 85-02 (No Requirenents) 3 C - Complete NC - No Changes Necessary NA - Not Applicable I - Incomplete E - Evaluating Actions Required 0408V 1

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~ TITLE REF. DOCUMENT

APPLICA81LITI. STATUS /DATE*

REMARKS A-5

.B&H Steam Generator NUREG-0844, SECY,86-97 B&N-PHR

.N/A' Tube Integrity-

'SECY 88-272 GL 85-02 (No' Requirements)

A-6 Mark I Containment NUREG-0408 Mark.I-BHR C/12-77 Short-Term Program A-7/

Mark I'Long-Term NUREC-0661 Mark I-BNR C/3-84

PUAR Approval Date D-01 Program NUREG-0661 Suppl. 1 GL 79-57 A-8 Mark II Containment

'NUREG-0808 Mark II-BWR N/A Pool Dynamic Loads NUREG-0487, Suppl. 1/2' NUREG-0802 SRP 6.2.1.1C GDC 16 A-9 Anticipated Transients NUREG-0460, Vol 4 All I

Complete U1 - 1990 Outage Hithout Scram 10 CFR 50.62

.-Complete U2 1991 Outage-A-10/

BHR Feedwater Nozzle NUREG-0619 BHR I

. Closure plan to be-MPA B-25 Cracking

' Letter from DG Eisenhut submitted in 1990 dated 11/13/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All C/11-88 Both units have upper Toughness 10 CFR 50.60 shelf energy above GL 82-26 50-ft-lb. Completion date is for submittal showing nil-ductility reference temperature shift.

A-12 Fracture Toughness of NUREG-0577, Rev. 1 PHR N/A Steam Generator and SRP Revision Reactor Coolant Pump 5.3.4 Supports 0408V 2

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NUMBER TITLE-REF. DOCUMENT APPLICABILITY-STATUS /DATE*

REMARKSr.

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y A-17 Systems Interactions

'Ltr:i'DeYoung to All

- NC Evaluated as part of:IPE' licensees'- 9/72 NUREG-1174,.NUREG '

1229, NUREG/CR-3922,-

NUREGICR-4261, NUREG/

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CR-4470, GL 89 (Nofrequirements)'

A-24/

'Oualification of Class NUREG-0588, Rev. 1 All C/11-85

. Unit 1l compliance MPA B-60 1E Safety-Related SRP 3.11

'(Unit 2)

.following restart' Equipment 10 CFR 50.49 14-86 (Unit 1)- from Fall, 1985 GL 82-09, GL 84-24 outags

'GL 85-15 A-26/

Reactor Vessel Pressure D0R Letters'to PHR

'NA MPA B-04 Transient Protection Licensees 8/76 NUREG-0224-NUREG-0371 SRP 5.2 GL 88-11 A-31 Residual Heat Removal

-NUREG-0606 All OLs After NA Shutdown Requirements RG 1.113,

-01/79 RG 1.139, SRP 5.4.7 A-36/

Control of Heavy Loads NUREG-0612 All C/4 C-10, Near Spent Fuel SRP 9.1.5 C-15 GL 81-07, GL.83-42, GL 85-11 Letter from DG Eisenhut dated 12/22/89 A-39 Determination of SRV NUREG-0802 BHR C/10-81 Addressed as part of A-7' Pool Dynamic Loads NUREGs-0763,0783,0802 and Pressure Transients

'NUREG-0661' SRP 6.2.1.1.C 0408V 3-

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'USI/MPA NUMBER-TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*

. REMARKS'

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A-40 Seismic Design

'SRP-Revisions,~NUREG/

All.

NC-Resolved with; resolution Criteria CR-4776. NUREG/CR-0054,.

for A-46'

.NUREG/CR-3480,.NUREG/'

.CR-1582,.NUREG/CR-1161, NUREG-1233,-NUREG-4776 NUREG/CR-3805 NUREG/CR-5347-NUREG/CR-3509 A-42/

Pipe Cracks in Boiling NUREG-0313 Rev. 1 BHR C/6-88 Some exceptions to MPA B-05 Hater Reactors NUREG-0313,.Rev. 2 G.L. 88-01 in GPC GL'81-03, GL 88-01' response.

A-43 Containment Emergency NUREG-0510, All NC Sump Performance NUREG-0869 Rev.-1 NUREG-0897, R.G.1.82 (Rev. 0), SRP 6.2.2 GL 85-22 No Requirements A-44 Station Blackout RG 1.155 All I

Completion no later NUREG-1032 than two years NUREG-1109

. following notification 10 CFR 50.63 of report acceptance A-45 Shutdown Decay Heat SECY 88-260 All NC Evaluation as part of Removal Requirements NUREG-1289 IPE hDREG/CR-5230 SECY 88-260 (No requirements)

A-46 Seismic Qualification NUREG-1030 All I

Unit 1 GIP final. report '

of Equipment in NUREG-1211/

2/90, Operating Plants GL 87-02, GL 87-03 Unit 1 modifications 12/91, Unit'2 GIP implementation 12/91 (tentative) 0408V 4

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' NUMBER TITLE REF. DOCUMENT

. APPLICABILITY: STATUS /DATE*~

REMARKS.

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A-47

. Safety. Implication ~

- NUREG-1217,.

All

- E-Response March,;1990 of Control Systems NUREG-1218' GL 89-19 A-48 Hydrogen Control 10 CFR 50.44-

'All,:except NC

~ Containment operates.-

Measures and Effects SECY 89-122 PWRs with

- with an'inerted-of Hydrogen Burns.

large dry

- atmosphere on Safety Equipment containments' A-49 Pressurized Thermal-RGs-1.154, 1.99 PWR-NA

' Shock SECY 82-465 SECY 83-288 SECY 81-687 10 CFR-50.61/

GL 88-11 i

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