ML19332E138
| ML19332E138 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/29/1989 |
| From: | Hairston W ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TASK-***, TASK-OR GL-89-21, NUDOCS 8912060273 | |
| Download: ML19332E138 (7) | |
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i Alabama Power Companyz -
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40 invemess Center Parkway i
Post Office Box 1295 Birmingham. Alabama 35201-
. Telephone 205 066-5581 4:;tg W.G.Heireton,llic sener vice President 1
Nuclear operations Alabama Power.
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the southem ekctresystem November 29 1989
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f Docket Nos. 50-348 50-364 l
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'U. S. Nuclear Regulatory Commission i
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ATTN: Document Control Desk Vashington, D. C. 20555 i
i' Gentlement Joseph M. Parley Nuclear Plant - Units 1 and 2 Response to Generic Letter 89-21 Request:for Information Concerning the Status of Implementetion of, Unresolved Safety Issue (USI) Requirements 1
iBy letter of October 19, 1989, the NRC requested information concerning the i
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status _of implementation'of Unresolved Safety Issue (USI) requirements.
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To comply with this request, Alabama Power Company undertook to review the j
appropriate correspondence in its files and prepared.the enclosed attachment. This attachment gives the current status of the USI
' i requirements and also references.the relevant supporting documentation.
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Please note that the remarks regarding the current status of each item are g
brief and do not describe all of the complex details of each USI requirement. :No new or revised commitments are contained in this u
t transmittal.
Should the NRC Staff desire more specific information regarding~ any particular USI requirement, then reference can be made to the i
specif t submittals identified in the attachment.
L Taking these constraints into account, the information provided is true to the
-best of my knowledge and belief.
If you have any questions, please advise.
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Respectfully submitted, O-V. G. Hairston, III VGH,III/JARamd 11.16 i
Enclosure L
i cc Mr. S. D. Ebneter Mr. E. A. Reeves Mr. G. F. Maxwell i
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8912060273 893129 K
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i FABI2Y Im rJ2AE FIA N.- W ITS 1'A W 2i
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USI/MFA NUMER TITIA REF. DOC M AFFLICASILITY STATWE/DATE M
q Based on IEtC' evaluation' A-1 Vater Hm==er SECY 84-119 All
.C-/ 9-80 NUREG-0927, Rev. 1
.sta et d in NUREG-0117,:.
IRNtEG-0993, Rev. 1 ~
Supp. 4.-(Unit 2 SER).
NUREG-0737, Item I.A.2.3 e
i SRP revisions A-2/
Asymmetric Blowdown NLEtEG-0609 PUR C / 9-80 Based'on IWtc evaluation j
MPA D-10 Loads on Reactor Primary GL 84-04, GDC-4 stated in NUREG-0117, Coolant Systems Supp. 4.-' (Unit: 2 SER) i
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A-3 Westinghouse Steam NUREG-0844 V-PVR C / 6-85 Based on APCo response Generator Tube Integrity SECY 86-97 to GL 85-02 (APCo to-
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SECT 88-272 1stC letter dated
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06-14-85).
GL 85-02 (No requirements)
See Note 1 on page 6.
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A-4 CE Steam Generator Tube NUttEG-0844, SECY 86-97 CE-FUR NA Integrity SECY 88-272 GL 85-02
-(No requirements)
A-5 B&W Steam Generator NUltEG-0844, SECY 86-97 B&V-FUR NA l
Tube Integrity SECY 88-272 GL 85-02 J
(No requirements) i A-6 Mark I Contair. ment NUREG-0408 Mark I-BUR NA Short-Term Program l
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g UFI/NFA NWWER TITIE REF. DOC M AFFLICABILITY STATWE/ BATE EMAMS A-7/
Mark I Long-Tern NUREG-0661 Mark I-BVR NA D-01 Progras NUREG4661 Supp.1 GL 79-37 A-8 Mark II Containment NUREG-0808 Mark II-BUR NA Fool Dynamic Loads NUREG-0487 Supp. 1/2 NUREG-0802 SRP 6.2.1.1C GDC 16 A-9 Anticipacec Transients NUREG-0460,'Vol. 4 All C'/ 10-88.
Based on NRC approval i
i Vithout Scram 10CFR50.62 stated in NRC to APCo SER dated 10-31-88..
A-10/
BVR Feedvater Nozzle NUREG-0619 BVR NA MPA B 75 Cracking Letter from DG Eisenhut dated 11/13/80.
GL'81-11 A-11 Reactor Vessel Material MUREG-0744, Rev. 1 All NC Based on IRC evaluation Toughness 10CFR50.60/
stated in NUREG-0117,.
82-26 Supplement.4. (WV 2 SER)
A-12 Fracture Toughness of NUREG-0577, Rev. 1 All NC Based on APCt> to NRC Steam Generator and SRP Revision letter dated OS-30-78.
I Reactor Coolant Famp 5.3.4 Supports A-17 Systems Interactions Ltr:.DeYoung to All NC Based on GL 89-18 which licersees - 9/72 states that USI A-17 NUREG-1174, N REG-1229, vill be resolved by IFE NUREG/CR-3922, NUREG/
(GL 86-20).
CR-4261, NUREG/CR-4470, i
GL 89-18 (No requirements)
A-24/
Qualificatfor. of Class NUREG-0588, Rev. 1 All C / 12-84 Based on NRC approval MPA B-60 1E Safety-Related SRP 3.11 stated in NRC'to APCo Equipment 10CFR50.49 SER dated 12-13-84.
i GL 82-09, GL 84-24 See Note 2 on page 6.
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USI/MFA l
MNBER TITLE REF. DOC M APPLICABILITY STATUS /DETE EMAES i
A-26/
Reactor Vessel Pressure DOR Letters to PUR C / 10-80 NUREG-0117, Supp. 4 MPA B-04. Transient Protection-Licensees 8/76 reported Unit 1 complete.
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NUREG-00224 Unit 2 was considered NUREG-0371 complete by issuance of SRP 5.2 Unit 2 Technical GL 88-11 Specifications.
See Note 3 on page 6.
A-31 Residual Heat Removal NUREG-0606 All OLs After Unit 1 - NA Shutdown Requirements RG 1.113, 01/79 Unit 2-Based on MtC approval RG 1.139 C / 3-81 stated in NUREG-0117 SRP 5.4.7 Supp. 5. (Unit 2 SER)
A-36/
Control of Heavy Loads NUREG-0612 All C~/ 7-84 Based on NRC approval C-10, Near Spent Fuel SRP 9.1.5 stated in NRC to APCo C-15 GL 81-07, GL 83-42, letter dated 07-25-84.
GL 85-11 Letter from DG Eisenhut dated
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12/22/80 A-39 Determination of SRV NUREG-0802 BUR NA l
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 NC Based on NUREG-1233 Criteria CR-4776, NUREG/CR-0054, which states that no NUREG/CR-3480, NUREG/
separate action is CR-1582, NUREG/CR-1161, proposed for resolution NUREG-1233, NUREG-4776, of USI A 40 for plants NUREG/CR-3805 covered by the NUREG/CR-5347 requirements of USI NUREG/CR-3509 A-46.
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Enclosure
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Nk; USI/MFA NINEER TITLE EEF. DOC M AFFLICABILITY STATW5/MTg 3 318 5 5 A-42/
Pipe Cracks in Boiling NUREG-0313, Rev. 1 BVR NA MFA B-05 Vater Reactors NUREG-0313, Rev. 2 GL 81-03, GL 88-01 A-43 Containment Emergency NUREG-0510, All NC AFCo issued letter to Sump Performance NUREG-0869, Rev. 1 designers 04-21-86 NUREG-0897, RG 1.82 which requested that AG (Rev. 0), SRP 6.2.2 1.82, Rev. I be utilized GL 85-22 for 50.59 revi ws deal-(No requirements) ing with replacement /
modification of thermal-insulation on RCS piping and components.
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A-44 Station Blackout RG 1.155 All I/Two years AFCo to NRC letter dated NUREG-1032 following 4-12-89 transmitted NUREG-1109 issuance of 10CFR50.63 blackout sub-10CFR50.63 NRC SER as mittal. AFCo still has to stated in implement hardware, pro-AFCo to 14tC cedure, and training letter dated modifications following-4-12-89.
receipt of SER.
A-45 Shutdown Decay Heat SECT 88-260 All NC Based on GL 88-20 Removal Requirements NUREG-1289 which states that NUREG/CR-5230 USI A-45 will be SECT S3-260 evaluated as a part of IPZ.
(No requirements)
A-46 Seismic Qualification NUREG-1030 All Unit 2 - NA AFCo is a member of Equipment in NUREG-1211/
of 500G.-
l Operating Plants GL 87-02, GL 87-03 Unit 1 - I 3
Valkdown to be completed during second refueling outage after final IWtc SER on GIF as stated in AFCo to NRC letter dated 10-09-89.
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m TITLE BEF. N AFFLICAEILITY ' STAN5/REFE M
2 A-47:
Safety Implication-NUREG-1217, NUREG-All' E'/ 3190 Based on evaluation I, ~
of Control Systems 1218
-being performed on
- GL 89-19' SG overfill protection-per GL 89-19.
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A-48 Hydrogen Contrcl 10CFR50.44 LAll,.except
-NA-Measures and Effects SECT 89-l'2 FURS with of Hydrogen Burns large. dry-on Safety Equipment containments A-49 Pressurized Thermal RGs 1.154, 1.99 FUR C / 11-88.
IEtC to AFCo letter dated Shock SECT 82-465 05-16-86 concluded AFCo-SECT 83-288 in compliance with SECT 81-687.
10CFR50.61.. The 11-88 10CFR50.61/
completion da.te is based GL 88-11 on FTS re-analysis on FNF Units 1'and 2 as reported in AFCo to IEtC letter dated 11-23-88 concerning GL 88-11.
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NOTES:
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Some coma n nents stated in the 06-14-85 letter have been revised or superceded as a result of revisions to the EPRI PVR Secondary Water l
Chemistry Guidelines and as a result of improvements in state-of-the-art secondary chemistry equipment and techniques. The changes have been made with the intent of maintaining a comprehensive program'to minimise steam generator tube degradstion.
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NRC Inspection Report 50-348, 364/89-23, dated 10-31-89, states that
"[FNP) is not considered to be in full compliance" with the 30 rule..
This inspection report closed an NRC finding in 1987 concerning grease change-out in Limitorque MOV gear boxes. The grease change-out was to be accomplished over the next two refueling outages and has been done i
I vith the exception of the second Unit 2 outage which is scheduled for Fall 1990. The-inspection report also identified one " unresolved" I
item involving the qualification of the Victoreen high range radiation monitor's junction box seal. The inspection report stated:
"This problem may be generic to the nuclear industry."
3.
The effect of neutron radiation on reactor vessel materials has been
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re-analyzed in response to G.L. 88-11. The results of the, i
re-evaluation were submitted by APCo to NRC letter dated 11-23-88.
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