U-601563, Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Results of Util Review & Reporting of Status of Implementation of USIs Encl
| ML19332D503 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 11/27/1989 |
| From: | Holtzscher D ILLINOIS POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| REF-GTECI-MI, REF-GTECI-SC, TASK-***, TASK-OR GL-89-21, U-601563, NUDOCS 8912040062 | |
| Download: ML19332D503 (7) | |
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U.601563 L30 89(1127) LP 8G.120 l
ILLIN0/8 POWER COMPANY IP j'
CLINTON POntR STATION, P.O. BOX 678, CLINTON. ILLIN0l$ OK.7
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I November'27, 1989 y
Docket No. 50 461 Nuclear Regulatory Commission Document. Control Desk
. Washington, D.C.
20555
Subject:
~
Clinton Power Station Response to Request for. Information Concerning Status' of Implementation of Unresolved Safety Issue (USI) Reauirements (Generic Letter 89-21)
Dear Sir:
Please find enclosed the results of the Illinois Power (IP) review
- and_ reporting of the status of implementation of Unresolved Safety Issues for which a final technical resolution has been achieved.
Sincerely yours, N)
D. L. Holtz her Acting Manager -
Licensing and Safety SFB/krm Enclosure ec:
Regional Administrator, Region III, USNRC NRC Clinton Licer. sing Project Manager NRC Resident Office Illinois Department of Nuclear Safety 8912040062 891127
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Enclosure to O-601563.
Page 1 of 6 LNRESOLVED SAFETY ISSUES FOR WHICH A FINAL TECHNICAL RESOIITTION HAS BEEN ACHIEVED USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS / MTE*/ REMARKS A-1 Water Hammer SEGY 84-119 All NC/SER Appendix C Section' NUREG-0927, Rev. 1 C.5 evaluated as no NUREG-0993, Rev. 1 meditional action NUREG-0737 Item I.A.2.3 required.
SRP revisions A-2/
Asymmetric Blowdown
-NUREG-0609 PWR NA MPA D-10 loads on Reactor GL 84-04, GDC-4 Primary Coolant Systems A-3 Westinghouse Steam NUREG-0844 W-PWR NA Generator Tube Integrity SEGY 86-97 SECY 88-272 GL 85-02 (No requirements)
A-4 CE Steam Generator NUREG-0844, SECY 86-97 CE-PWR NA Tube 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) i l
E Mark I Containment NUREG-0408 Mark I-BWR NA
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A-6 Short-Term Program l
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- C - Complete NC - No Changes Necessary NA - Not Applicable I - Incomplete E - Evaluating Actions Required
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Enclosure to G-601563.
Page 2 of 6 USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*/RENARKS A ~i/D-01 Mark I long-Term NUREG-0661 Mark I-BWR NA Program NUREG-0661 Supp. 1 GL 79-57 A-8 Mark II Containment NUREG-0808 Mark II-BWR
.NA Fool Dynamic Loads NUREG-0487,.Supp. 1/2 NUREG-0802 SRP 6.2.1.1C GDC 16 A-9 Anticipated Transients NUREG-0460, Vol. 4 All C (10/85)/
Without Scram 10CFR50.62 SSER *6, Section 15.2.1 A-10/
BWR Feedwater Nozzle NUREG-0619 BWR C (11/86)/USAR Section MPA B-25 Cracking Letter from DG Eisenhut 5.3.3.1.4.5.
dated 11/13/80 NRC Letter GL 81-11 March 1, 1988, Docket #50-461.
151 Manual App. 4.
transmitted by IPC**
1etter U-600753 dated 11/7/86.
A-11 Reactor Vessel NUREG-0744, Rev. 1 All C (7/82)/SSER 1, Sections Material Toughness 10CER50.60/82-26 5.3.1, 2 and 3 A-12 Fracture Toughness of NUREG-0577, Rev. 1 PWR NA Steam Generator and SRP Revision 5.3.4 Reactor Coolant Pump Supports A-17 Systems Interactions Ltr: DeYoung to All NC/GL 89-18 did not licensees - 9/72 require actions of IP.
NUREG-1174, NUREG-1229, NUREG/CR-3922, NUREG/CR-4261 NUREG/
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Enc 1: sura to C-601563 Page 3 of 6 USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STATUS /DATE*/ REMARKS CR-4470, GL 89-18 (No requirements)
A-24/
Qualification of Class NUREG-0588, Rev. 1 All C (9/86)/SSER 5. Sections MPA B-60 1E Safety-Related SRP 3.11 3.11.3.2, 3.11.5.
Equipment 10CFR50.49 SSER 6, Sections 3.11, CL 82-09, GL 84-24, 7.7.3.
GL 85-15 SSER 7, 3.10.1.
A-26/
Reactor Vessel DOR Letters to PWR I/due 4/90 MPA B-04 Pressure Transient Licensees 8/76 IPC letter U-601317 Protection NUREG-0224 dated 12/6/88 NUREG-0371 responding to GL 88-11 SRP 5.2 identifies need for GL 88-11 Tech. Spec. change.
A-31 Residual Heat Removal NUREG-0606 All OLs After C (2/82)/SER Section Shutdown Requirements RG 1.113, 01/79 5.4.2, (Table C-1).
RG 1.139 A-31 resolved SRP 5.4.7 by NRC in 5/78 by issue of SRP Section 5.4.7.
SER was issued in 1982; implemented prior to licensing.
A-36/
Control of Heavy Loads NUREG-0612 All I/(procedure changes C-10, C-15 Near Spent Fuel SRP 9.1.5 due 9/90). SSER 5, GL 81-07, GL 83-42, Section 9.1.5.
GL 85-11 Addftional procedural Letter from DG Eisenhut controls to be dated 12/22/80 implemented prior to next refueling.
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Enclosure to C-601563 Page 4 cf 6 USI/MPA NUMBER TITLE REF_ DOCUMENT APPLICABILITY STATUS /DATE*/ REMARKS A-39 Determination of SRV Pool NUREG-0802 BWR C (1/86)/
Dynamic Ioads and Pressure NUREGs-073,0783,0802 SER, Section 6.2.1.3, Transients NUREG-0661 SSER 5, Section 6.2.1 SRP 6.2.1.1.C A-40 Seismic Design Criteria SRP Revisions, NUREG/
All NC/SSER 7, Section CR-4776, NUREG/CR-0054, 3.10.1 NUREG/CR-3480, NUREG/
CR-1582 NUREC/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 BWR I/ Tech. Spec. chan6e MPA B-05 Water Reactors NUREG-0313, Rev. 2 required GL 81-03, GL 88-01 (due 2/90).
SSER 1, Section 5.2.3.
A-43 Containment Emergency NUREG-0510, All NC/USI A-43 and GL 85-22 Sump Performance NUREG-0869, Rev. 1 did not contain NUREG-0897, RG 1.82 requirements for IPC.
(Rev. 0), SRP 6.2.2 GL 85-22 (No requirements)
A-44 Station Blackout RG 1.155 All I/due 5/90, IPC letter NUREG-1032 U-601427 dated 4/16/89 NUREG-1109 provided the results of 10CFR50.63 the IPC review on SBO.
All actions scheduled to be completed by this date are complete. Additional procedure changes will be made by 5/90.
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l Enclosure to C-601563 Page 5 of 6 USI/MPA TITI4 REF. DOCUMENT APPLICABILITY STATUS /MTE*/ REMARKS I
NUMBER A-45 Shutdown Decay Heat SECY 88-260 All I/due 9/92.
Removal Requirements NUREG-1289 IPC letter U-601549, dated NUREG/CR-5230 10/27/89 (A-45 now SECY 88-260 included in Individual (No requirements)
Plant Examination GL 88-20 Program).
A-46 Seismic Qualification NUREG-1030 All NC/SSER 7, Section 3.10.1 of Equipment in NUREG-1211/
Operating Plants GL 87-02, GL 87-03 A f.7 Safety Implication of NUREG-1217, All E/(due 3/2/90)
Control Systems NUREG-1218 GL 89-19 A-48 Hydrogen Control Measures 10CER50.44 All, except PWRs I/due 12/90 for Emergency and Effects of Hydrogen SECY 89-122 with large dry Operating Procedures (EOP)
Burns on Safety Equipment containments completion. All equipment is installed. IP will.
submit documentation demonstrating compliance within 6 mos. of issuance of the General Hydrogen Control Program SER.
IPC is developing Hydrogen Control E0P. Hydrogen mitigation procedures are in place.
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r-g Enclosure to C-601563:
Fage 6 of 6 USI/MPA NUMBER TITLE REF. DOCUMENT APPLICABILITY STA7US/MTE*/ REMARKS A-49 Pressurized Thermal RGs 1.154, 1.99 FWR-NA Shock SECY 82-465 SECY 83-288 SECY 81-687 10CFR50.61/GL 88-11
- SER/SSER - Safety Evaluation Report for Clinton Power Station - NUREG+0853~
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