ML19353A886

Responds to 891019 Generic Ltr 89-21 Re Request for Info Concerning Status of Implementation of USI Requirements. Table of USIs for Which Final Technical Resolution Has Been Achieved Encl

ML19353A886
Person / Time
Site:	Vogtle
Issue date:	11/30/1989
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR ELV-01104, ELV-1104, GL-89-21, NUDOCS 8912080038
Download: ML19353A886 (8)

Text

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• Georg.a Power Company

• -i. 333 Paednont Avenue  ;

'g' Atlanta. Gecng a 30Xe Telephone 434 $P6 3195 '

Wing A@ets 40 invernets Center Pakway  !

Pos: Othee Box 10i45 j

$$Uo$IEN#

November 30, 1989  !

1%xto.vt+,n re n &m W. G. Hainton, Ill  !

Sen or yet e Prescent NuWar Omratons ELV-01104  !

0130 ,

t Docket Nos. 50-424  ;

50-425 i U. S. Nuclear Regulatory Commission  !

ATTN:- Document Control Desk Washington, D. C. 20555 r

Gentlemen:

V0GTLE ELECTRIC GENERATING PLANT

.I RESPONSE TO GENERIC LETTER 89-21 NRC Generic Letter 89-21, " Request for Information-Concerning Status of -

Implementation of Unresolved Safety Issue (USI) Requirements", was issued on ,

October 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 requirec9ts 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, the' table of USIs referenced in-the generic-letter is provided as .

an enclosure with the status of each USI indicated. Supporting documentation is l

available for review upon request. The status indicated is consistent with the L 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. In that regard, this transmittal serves merely as an index and does not contain any new or revised commitments. Taking 4 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, Jh.k h n d w k W. G. Hairston, III L

i  :

WGH,III/AFS/gm

Enclosure:

Unresolved Safety Issues for Which a Final l

l- Technical Resolution has been Achieved kp xc (see next page) 1.

l 8912080038 891130 PDR ADOCK 05000424 P PNU

IV je i '.. ..

GeorgiaPower I U. S. Nuclear Regulatory Commission ELV-01104 Pace Two xc: Georoia Power Company Mr. C. K. McCoy Mr. G. Bockhold, Jr.

Mr. P. D. Rushton Mr. R. M. Odom NORMS U. S. Nuclear Reaulatory Commissi.2D Mr. S. D. Ebneter, Regional Administrator Mr. J. B._llopkins, Licensing Project Manager, NRR Mr. J. F. Rogge,. Senior Resident Inspector, Vogtle l

I l

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-UNRESOLVED SAFETY ISSUES FOR WHIC'1 A FINAL TECHNICAL RESOLUTION HAS BEEN ACHIEVED

.USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*- REMARKS A-1 Water Hammer SECY 84-119 All C FSAR 5.4.2.2, NUREG-0927, Rev. 1 Units 1 & 2 - June.1985 10.4.7, -

NUREG-0993, Rev. I 10.4.9.1.1 NUREG-0737 Item SER 10.4.7, I.A.2.3 10.4.9 SRP revisions A-2 Asymmetric Blowdown NUREG-0609 PWR .C- FSAR 3.9.N.2.3, MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 Units 1 & 2 - June 1985 3.9.N.2.4, Coolant Systems 3.9.N.2.5 3.9.N.3 SER 3.9.2.3, 3.9.2.4 A-3 Westinghouse Steam NUREG-0844 W-PWR C FSAR 5.4.2.

Generator Tube' Integrity SECY 86-97 Unit 1 - August 1986 SER 5.4.2 App. C SECY 88-272 Unit 2 - February 1989 -SSER 3 - 5.4.2.2.2 GL 85 SSER 8 - 5.4.2.2.2' No requirements A-4 CE Steam Generator Tube NUREG-0844, SECY 86 CE-PWR NA Integrity SECY 88-272-GL 85-02 No requirements A-5 B&W Steam Generator NUREG-0844, SECY 86-97 B&W-PWR NA Tube Integrity SECY 88-272 GL 85-02 No requirements

• C - COMPLETE NC - NO CHANGES NECESSARY NA - NOT APPLICABLE I - INCOMPLETE E - EVALUATING ACTIONS REQUIRED

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

A-6 Mark I Containment- NUREG-0408 Mark-I-BWR NA

.Short-Term Program A-7/ Mark I Long-Term NUREG-0661 Mark I-BWR NA D-01 Program NUREG-0661 Suppl. I GL 79-57 A-8 Mark II Containment NUREG-0808 Mark II-BWR NA 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 C FSAR 7.7.1.11, Without Scram 10 CFR 50.62 Units 1 & 2 - October, 1988 15.8 SSER 8-15.8 Letters to NRC SL-2724, 3651, 4368. Letter from NRC dated 10-3-88 A-10/ BWR Feedwater Nozzle NUREG-0619- BWR NA' MPA B-25 Cracking Letter from DG Eisenhut dated 11/13/80 GL 81-11 A-11 Reactor Vessel Material NUREG-0744, Rev. 1 All .C FSAR 5.3.1 Toughness 10 CFR 50.60/ Units 1 & 2 - June 1985 SER 5.3.1 82-26 A-12 Fracture Toughness of NUREG-0577, Rev. 1 PWR NA No back-fit Steam Generator and SRP Revision requirement Reactor Coolant Pump 5.3.4 per SRP.

Supports

USI/MPA ,,

NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE* REMARKS A-17 Systems Interactions Ltr: DeYoung to All NC . SER App. C licensees - 9/72 Will be evaluated NUREG-1174, NUREG-1229 as part of IPE-NUREG/CR-3922, Report due to NUREG/CR-4261, NUREG/ NRC September CR-4470, GL 89-18 1992. Review No requirements of Events at Nuclear-Power Plants-Operating Experience Program Procedures 00414-C &

81050-C A-24/ Qualification of Class NUREG-0588, Rev. 1 All C FSAR 3.11 MPA B-60 IE Safety-Related SRP 3.11 Unit 1 - January 1987 SSER 5 - 3.11 Equipment 10 CFR 50.49 Unit 2 - February 1989 SSER 8 - 3.11 GL 82-09, GL 84-24 GL 85-15 A-26/ Reactor Vessel Pressure DOR, Letters to PWR C FSAR 5.2.2,5.3.2 MPA B-04 Transient Protection Licensees 8/76 Units 1 & 2 - November 1988 SER 5.2.2, NUREG-0224 SSER 2 - 5.2.2.2, NUREG-0371 GL 88-11 SRP 5.2 Response dated GL 88-11 11-28-88 Letter No.ELV-00014.

Follow-up letter to GL 88-II,ELV-00571 Request to Revise Tech Spec. Heatup and Cooldown Curves dated 7-28-89 A-31 Residual Heat Removal NUREG-0606 All Ols After C FSAR 1.9.139.2, Shutdown Requirements RG 1.113, 01/79. Units 1 & 2 - June 1985 5.4.7 RG 1.139 SER 5.4.7.6 SRP 5.4.7

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USI/MPA ,

NUMBER . TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE* REMARKS A-36/ Control of Heavy Loads NUREG-0612 All- C .

FSAR 9.1.5 i C-10, Near Spent Fuel. SRP 9.1.5- Units 1 & 2 - June 1985 SER 9.1.5, C-15 GL 81-07, GL 83-42, Appendix I GL 85-11 Letter from DG Eisenhut dated 12/22/80 A-39 Determination of SRV NUREG-0802 BWR NA Pool Dynamic Loads NUREGs-0763, 0783, 0802 and Pressure Transients NUREG-0661 SRP 6.2.1.1.C A-40 Seismic Design SRP Revisions, NUREG/ All C FSAR 3.7, 3.8, 3.9 &

Criteria CR-4776, NUREG/CR-0054 Units 1 & 2 - June 1985 3.10 SER App. C NUREG/CR-3480, NUREG/

CR-1582, NUREG/CR-Il61, NUREG-1233, NUREG-4776 NUREG/CR-3805 NUREG/CR-5347 NUREG/CR-3509-A-42/ Pipe Cracks in Boiling NUREG-0313, Rev. I BWR NA MPA B-05 Water Reactors NUREG-0313, Rev. 2 GL 81-03, GL 88-01 A-43 Containment Emergency NUREG-0510, All C FSAR 6.2.2.2.2.3.2 Sump Performance NUREG-0869, Rev. 1 Units 1 & 2 - October 1985 6.3.2.2.4 NUREG-0897, R. G. 1.82 SER App. C (Rev. 0), SRP 6.2.2 SSER I - 6.2.2 GL 85-22 No Requirements

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

SER App. C A-44 Station Blackout RG 1.155 All I 580 Response letter-NUREG-1032 #ELV-00432 dated _

'NUREG-1109 4-12-89.

10 CFR 50.63 Adminstrative and design changes scheduled to be

. completed one year from receipt of NRC approval of 580 analysis report.

A-45 Shutdown Decay Heat SECY 88-260 All NC SER App. C. Will Removal Requirements NUREG-1289 be evaluated as NUREG/CR-5230 part of IPE SECY 88-260 Report to NRC No requirements due September 1992 per ELV-00994.

A-46 Seismic Qualification NUREG-1030 All C SER 3.9.2 and of Equipment in NUREG-1211/ 3.10 - evaluated Operating Plants GL 87-02, GL 87-03 during licensing phase.

SER App. C A-47 Safety Implication NUREG-1217, NUREG- All E GL 89-19 response of Control Systems 1218 deadline March 19, GL 89-19 1990 A-48 Hydrogen Control 10 CFR 50.44 All, except NA Measures and Effects SECY 89-122 PWRs with large of Hydrogen Burns dry containments on Safety Equipment

'9 USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE* REMARKS A-49 Pressurized Thermal RGs 1.154, 1.99 PWR C FSAR 5.2.2.10, Shock SECY 82-465 Units 1 & 2 - November- 5.3.1, 5.3.2 SECY 83-288 1988 SER App. C SECY 81-687 10 CFR 50.61 GL 88-11 i

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