ML20210R338

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Requests Review of Encl plant-specific List & Addition of Omitted Significant Actions & Dates When All Aspects of Each Identified Requirement Completed.Requests Response by 860531
ML20210R338
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 05/02/1986
From: Silver H
Office of Nuclear Reactor Regulation
To: Wilgus W
FLORIDA POWER CORP.
References
TASK-***, TASK-TM NUDOCS 8605160333
Download: ML20210R338 (16)


Text

3 h Q Obo May 2,1986 o

Docket No. 50-302 DISTRIBUTIO_N ITocket Filg)

BGrimes MU PUH JPartlow Mr. Walter S. Wilgus L PDR Ringram Vice President, Nuclear Operations PBD#6 Rdg HSilver Florida Power Corporation FMiraglia Gray File ATTN: Manager, Nuclear Licensing OELD HSmith

& Fuel Management ACRS-10 SScott P. O. Box 14042; M.A.C. H-3 EJordan St. Petersburg, Florida 33733

Dear Mr. Wilgus:

The Comptroller General in a Report to the Congress dated September 19,.1984, stated "NRC needs better management controls to ensure implementation of generic issue solutions." To correct this situation, the Nuclear Regulatory Commission is working on a long-term program which will improve its documentation on the status of power reactor licensees' implementation of approved regulatory improvements.

To assist me in developing this information for Crystal River Unit No. 3, please review the enclosed plant-specific list, add omitted significant actions to the list, and provide the date that all aspects of each identified requirement were completed / implemented or are expected to be completed.

For each requirement that has been completed, enter " completed" under the Status column and the date the item was completed.

For requirements that have not been completed / implemented, provide the projected date and enter " projected" under the Status column.

I do not expect or want a major >' fort made to obtain precise dates. Rather, I will accept readily-known w best-estimate dates for actions that have been completely implemented.

For example, the year only would be acceptable for completions prior to 1984; the month as well as year is needed for requirements completed after that time.

For projected completions / implementations in 1986, use month and year. Use year only for-projections thereafter. Please provide a response in the form of a marked up listing by May 31, 1986.

In the future, NRR will need estimated dates prior to issuance of the safety evaluation so that the estimated schedule may be included in the evaluation.

l This request is covered by OMB Clearance Number 3150-0011, which expires September 30, 1986.

Sincerely, "GN.E!!I Harley Sbv$l%Th y!'.ner, P'r6 Ject Manager PWR Project Directorate #6 Division of PWR Licensing-B

Enclosure:

As stated cc w/ enclosure: See next pag Raw PB PBD-6 I

6 HSiJ er;cf RWeller Ji Iz 5/l/86 5// /86 5/1 8605160333 860502 PDR ADOCK 05000302 P

PDR y

Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc:

Mr. R. W. Neiser State Planning and Development Senior Vice President Clearinghouse and General Counsel Office of Planning and Budget Florida Power Corporation Executive Office of the Governor P. O. Box 14042 The Capitol Building St. Petersburg, Florida 33733 Tallahassee, Florida 32301 Mr. P. McKee Mr. F. Alex Griffin, Chairman Nuclear Plant Manager Board of County Commissioners Florida Power Corporation Citrus County P. O. Box 219 110 North Apopka Avenue Crystal River, Florida 32629 Inverness, Florida 36250 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814

~

Resident Inspector U.S. Nuclear Regulatory Commission Route #3, Box 717 Crystal River, Florida 32629 Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. Allan Schubert, Manager Public Health Physicist Department of Health and Rehabilitative Services 1323 Winewood Blvd.

Tallahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304

'I

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112 FACILITY IMPLEMENTATION 03/31/86 ACILITY: CRYSTAL RIVER 3 LANT LOCATION: 7 MI NH OF CRYSTAL RIVER, FLA LICENSED P0HER: 2544 MHT PROJECT MANAGER: H. SILVER OCKET NUMBER:

050-00302 DESIGN P0HER:

0825 MNE BRANCH CHIEF:

J. STOLZ RCH/ ENGINEER: GIL NSSS VENDOR:

B&H LIC. ASSISTANT:

R. INGRAM E INSPECTOR:

T. STETKA LIC ACT LICENSEE AC NO.

MPA 4 TITLE COMPLETE STATUS DAIE 04548 A-01 to CFR 50.55 A(G) - ISI 07/22/80C 08985 A-02 APPENDIX I - ALARA 06/27/84C 10907 A-02 APPENDIX I - ALARA 01/01/70C 07065 A-03 SECURITY REVIEHS-MODIFIED AMENDMENT PLANS 01/24/79C 11378 A-09 PRESSURE VESSEL BELTLINE MATERIAL SURVEILLANCE 05/19/80C 10729 A-10 CONTINGENCY PLANNING 04/02/82C 10733 A-11 GUARD TRAINING PLANS 03/04/83C 10731 A-12 VITAL AREA ANALYSIS 04/14/82C 04549 A-14 10CFR 50.55 A(G) - INSERVICE TESTING 05/02/86 12561 A-15 QUALITY ASSURANCE REQUEST REGARDING DIESEL GENARAT 04/11/80C 47555 A-16 QUALIFICATIONS OF EXAMINATION, INSPECTION, TESTING 04/29/82C 51083 A-17 INSTRUMENTATION TO FOLLOH THE COURSE OF AN ACCIDEN 05/01/86 55703 A-18 TECH SPECS AFFECTED BY 50.72 AND 50.73 (GL 83-43) 08/30/86 59085 A-20 10 CFR 50.62 OPERATING REACTOR REVIENS N//S /

59949 A-21 10 CFR 50.61, PRE?SURIZED THERMAL SHOCK RULE 07189 B-02 FIRE PROTECTION 07/27/79C 08377 B-03 PHR MODERATOR DILUTION 08/01/80C 06720 B-04 REACTOR VESSEL OVERPRESSURE PROTECTION 07/03/79C 07469 B-10 BURNABLE POISDN ROD FAILURE - B&W 09/02/78C 10845 - B-14 CEA GUIDE TUBE HEAR 07/24/81C O

8

1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.

113 FACILITY IMPLEMENTATION 03/31/86~

SSTAL RIVER 3 (CONTINUATION)

LIC ACT LICENSEE C.NO.

MPA 8 TITLE COMPLETE STATUS R&lf

!8881 B-17 TECH SPEC SURVEILLANCE FOR HYDRAULIC SNUBBERS 02/02/82C 1755G B-18 HORTHINGTON RHR PUMP SHAFT INTEGRITY 09/02/78C 0317 B-20 CONTAINMENT LEAKAGE DUE TO SEAL DETERIORATION 08/25/80C 0379 B-21 LOSS OF 125-V DC BUS VOLTAGE HITH LOSS OF ANNUNCIA 11/30/79C 18883 B-22 TECH SPEC SURVEILLANCE REQUIREMENTS FOR MECHANICAL 02/19/81C 0017 B-23 DEGRADED GRID VOLTAGE 08/24/83C

>2596 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 04/11/83C 0211 B-24 VENTING AND PURGING CONTAINMENTS HHILE AT FULL P0H 03/16/81C 0254 B-26 INADVERTANT SAFETY INJECTION DURING C00LDOWN 09/14/79C 18702 B-39 PHR PRESSURE - TEMPERATURE LIMIT TECH SPECS 03/16/81C 1109 B-41 FIRE PROTECTION - FINAL TECH SPECS (INCLUDES SER S 10/14/80C 1861 B-42 TMI FOLLON UP - ALL PLANTS 03/16/81C 1796 B-43 PHR FEEDWATER LINE CRACKS 12/09/80C 2451 B-44 L'ESSONS LEARNED IMPLEMENTATION 04/17/81C LO637 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C LO638 B-44 LESSONS LEARNFD IMPLEMENTATION 05/05/80C LO639 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C LO626 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C iO627 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C LO628 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C LO629 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C iO630 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C

,0631 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C O

+ - - -

t-1208731 -0 01 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.

114:

FACILITY IMPLEMENTATION 03/31/86

RYSTAL RIVER 3 (CONTINUATION)

LIC ACT LICENSEE

'AC NO.

MPA 3 TITLE COMPLETE STATUS Balg 130632 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C 130633 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C 130634 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C 130335 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C 130636 B-44 LESSONS LEARNED IMPLEMENTATION 05/05/80C 112883 B-45 HASH 1400 EVENT V, " PRIMARY COOLANT SYSTEM PRESSUR 04/20/81C 112599 B-46 ANALYSIS OF TURBINE DISC CRACKS 08/20/81C 112731 B-47 ECCS; CLAD SHELLING AND RUPTURE 09/09/80C 112743 B-48 ADEQUACY OF STATION ELECTRIC DISTRIBUTION VOLTAGE 04/19/84C 143076 B-52 REVIEH OF SAFETY ASPECT OF INADVERTENT SAFETY ACTI 06/15/81C 142121 B-57 DHR CAPABILITY 10/05/83C 142902 B-59 MASONRY HALL DESIGN 03/15/86 142512 B-60 ENVIRONMENTAL QUALIFICATION 02/28/85C 1426G4 B-61 LOSS OF NDH CLASS IE ISC P0HER 07/28/82C 142734 B-62 ESF RESET CONTROL DESIGN DEFICIENCY 07/02/81C 143912 B-63 INTERIM PROCEDURES FOR SHORT TERM BLACKOUT

2/16/81C 143263 B-64 B&C INDUCED FLUX ERRORS 04/22/82C 147166 B-66 NATURAL CIRCULATION C00LDOHN 06/30/86 146831 B-69 IEB 80-4 MAINSTEAM LINE BREAK HITH CONTINUED FEEDH 10/21/82C 149729 B-72 NUREG 0737 TECN SPECS (GENERIC LETTER 82-16) 09/23/85C 152749 B-76 ITEM 1.1 - POST TRIP REVIEH; PROGRAM DESCRIPTION &

06/10/86 l

152830 B-77 ITEM 2.1 - EQUIPMENT CLASSIFICATION 8 VENDOR INTER 04/01/87 l

152911*

B-78 ITEMS 3.1.1 & 3.1.2 -POST MAINTENANCE TEST PROCEDU 09/09/85C

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115 FACILITY IMPLEMENTATION 03/31/86 RYSTAL RIVER 3 (CONTINUATION)

LIC ACT LICENSEE AC NO.

MPA 8 TITLE COMPLETE STATUS DAlf 52992 B-79 ITEM 3.1.3 - POST MAINTENANCE TESTING - CHANGES TO 09/11/85C 53066 B-80 ITEM 4.1 - REACTOR TRIP SYSTEM RELIABILITY - VENDO 09/09/85C I

53119 B-81 ITEMS 4.2.1 & 4.2.2 -PREVENTATIVE MAINT PROG FOR R 04/21/86 33169 B-82 ITEM 4.3 - AUTOMATIC ACTUATION OF SHUNT TRIP ATTAC 03/11/85C 54527 B-83 TECH SPECIFICATIONS COVERED BY GENERIC LETTERS 83-09/30/86 53581

, B-85 SALEM ATHS 1.2 DATA CAPABILITY 09/06/85C 53664 B-86 SALEM ATHS 2.2 S-R COMPONENTS 04/01/87 53747 B-87 SALEM ATHS 3.2.1 8 3.2.2 S-R COMPONENTS 09/09/85C 3830 B-88 SALEM ATHS 3.2.3 T.S. S-R COMPONENTS 53906 B-89 SALEM ATHS 4.2.3 & 4.2.4 LIFE COMPONENTS 55351 B-90 SALEM ATHS 4.3 H AND B&W T.S.

53953 B-91 SALEM ATHS 4.4 B&H TEST PROCEDURES 04/30/86 54057 B-92 SALEM ATHS 4.5.1 DIVERSE TRIP FEATURES 09/09/85C 53974 B-93

. SALEM ATHS 4.5.2 8 4.5.3 TEST ALTERNATIVES

$8889 C-01 PHR SECONDARY HATER CHEMISTRY MONITORING REQUIREME 08/19/80C h8880 C-06 PUMP SUPPORT-LAMELLAR TEARING 04/17/81C h8882 C-07 FUEL NANDLING ACCIDENT INSIDE CONTAINMENT 05/06/80C 37983 C-10 CONTROL OF NEAVY LOADS OVER SPENT FUEL POOL (PHASE 07/13/84C 3647 C-14 AUXILIARY FEEDHATER SEISMIC QUALIFICATION 08/09/83C f2220 C-15 CONTROL OF NEAVY LOADS - PNASE II (FDLLOHUP OF MPA 06/28/85C

%8054 C-16 UTILITY RESPONSES T0_ STAFF RECOMMENDATIONS CONCERN 04/30/86 h7056 D-08 DEFICIENCY IN CHEM ADDITION TO CONTAINMENT SPRAYS 07/03/79C b8606 D-08 DEFICIENCY IN CHEM ADDITION TO CONTAINMENT SPRAYS 01/01/70C

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116 FACILITY IMPLEMENTATION 03/31/86 lRYSTAL RIVER 3 (CONTINUATION)

LIC ACT LICENSEE

'AC NO.

MPA 9 TITLE COMPLETE STATUS RAIE l08843 D-10 ASYMMETRIC LOCA LOADS 01/11/84C 110105 D-11 FISSION GAS RELEASE 02/25/80C 108006 D-13 B8H SMALL BREAK ERROR 07/03/79C 108884 D-14 REACTOR VESSEL HELD - HIRE DEFICIENCY 10/29/79C 111007 D-14 REACTOR VESSEL HELD - HIRE DEFICIENCY 01/01/70C 112321 D-15 HIGH ENERGY LINE BREAK & CONSEQUENTIAL SYSTEM FAIL 01/31/84C K3037 D-17 DEFINITION OF OPERABLE 07/10/81C l'6559 D-17 DEFINITION OF OPERABLE 07/10/81C 151734 D-18 NUREG 0630 CLADDING MODELS (B8H PLANTS) 07/12/83C 155851 D-19 DIESEL GENERATOR RELIABILITY TECH SPECS (GL 84-15) 09/18/85C 107468 E-01 SPENT FUEL POOL EXPANSIONS 11/17/80C 111296 E-03 CORE RELOADS REQUIRING PRIOR NRC APPROVAL 07/03/79C 144012 F-01 I. A.1.1 SHIFT TECHNICAL ADVISOR 02/05/82C 44080 F-02 I.A.1.3 SHIFT MANNING 06/30/83C 44151 F-03 I.A.2.1 UPGRADING OF RO AND SRO TRAINING 04/06/83C 44222 F-04 I.C.1.2/3.A EMERGENCY OPERATING PROCEDURES GENERIC 06/01/84C M4292 F-05 I.C.1.2/3.5 PROCEDURES GENERATION PACKAGES (NUREG 09/30/86-H7205 F-06

- I.C.5 FEEDBACK OF OPERATING EXPERIENCE 12/07/81C 47277 F-07 I.C.6 CORRECT PERFORMANCE OF OPERATING ACTIVITI 12/07/81C 151153 F-08 I.D.1.1 DETAILED CONTROL ROOM DESIGN REVIEN PROGRA 02/07/84C l51233 F-09 I.D.2 SAFETY PARAMETER DISPLAY SYSTEM 07/30/86 44363 F-10 II.B.1 RCS HIGH POINT VENTS 09/08/83C 47929 ~

F-11 II.B.2 PLANT SHIELDING 11/01/83C O

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LIC ACT LICENSEE LC NO.

MPA 8 TITLE COMPLETE STATUS DATf.

44431 F-12 II.B.3 POST ACCIDENT SAMPLING 11/12/85C i4501 F-13 II.B.4 TRAINING FOR MITIGATING CORE DAMAGE 04/06/83C i4571 F-14 II.D.1 RV AND SV TRAINING 04/30/86 44668 F-15 II.E.1.1 AFH SYSTEM EVALUATION 04/30/84C 44708 F-16 II.E.1.2.1 AFH SYSTEM INITI ATION 03/16/83C 44750 F-17 II.E.1.2.2 AFH SYSTEM FLOH INDICATaDN 03/16/83C 44769 F-18 II.E.4.1 DEDICATED HYDROGEN PENETRATION 08/19/81C 44840 F-19 II.E.4.2 CONTAINMENT ISOLATION DEPENDABILITY 04/06/83C 44911 F-20 II. F.1.1 NOBLE GAS MONITOR 12/09/81C 44982 F-21 II. F.1. 2 IODINE / PARTICULATE SAMPLING 12/09/81C 65053 F-22 II.F.1.3 CONTAINMENT HIGH RANGE MONITOR 01/12/82C 47590 F-23 II. F.1. 4 CONTAINMENT PRESSURE INSTRUMENT 07/22/82C 47661 F-24 II.F.1.5 CONTAINMENT HATER LEVEL INSTRUMENT 07/22/82C 47732 F-25 II.F.1.6 CONTAINMENT HYDROGEN MONITOR 07/22/82C 45124 F-26 II.F.2 INSTRUMENTS FOR DETECTION ON INADEQUATE 02/15/87 42792 F-27 II.K.2.9 FMEA ON ICS 04/19/82C 45183 F-28 II.K.2.10 SAFETY GRADE ARTS 11/02/81C 45190 F-29 II.K.2.11 CONTINUED OPERATOR TRAINING AND DRILLIN 02/08/82C 43426 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 04/29/82C 45197 F-30 II.K.2.13 THERMAL-MECHANICAL REPORT 06/05/84C 45204 F-31 II.K.2.14 LIFT FREQUENCY OF PORVS AND SVS 05/25/82C 45211 F-32 II.K.2.16 RCP SEAL DAMAGE 01/21/82C 45217 '

F-33 II.K.2.17 POTENTIAL FOR VOIDING IN RCS 12/10/81C

l 1208751-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.

118 FACILITY IMPLEME-NTATION 03/31/86.

3YSTAL RIVER 3 (CONTINUATION)

LIC ACT LICENSEE AC NO.

MPA 8 TITLE CONPLETE STATUS D&IE 45223 F-35 II.K.2.20 SYSTEM RESPONSE TO SB LOCA 08/20/81C 45268 F-36 II.K.3.1 AUTO PORV ISOLATION 06/28/84C 45314.

F-37 II.K.3.2 REPORT ON PORV FAILURES 09/30/83C 45333 F-38 II.K.3.3 REPORTING SV AND RV FAILURES AND CHALLE 08/09/85C 45435 F-39 II.K.3.5 AUTO TRIP OF RCPS 02/22/83C 45619 F-47 II.K.3.17 ECCS OUTAGES 10/06/83C 45815 F-57 II.K.3.30 SB LOCA METHODS 08/30/85C 48156 F-58 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 10/31/86 45935 F-63 III.A.1.2 TECHNICAL SUPPORT CENTER 06/30/87 46006 F-64 III.A.1.2 OPERATIONAL SUPPORT CENTER 06/30/87 46078 F-65 III.A.1.2 EMERGENCY OPERATIONS FACILITY 06/30/87 46150 F-66 III.A.1.2 NUCLEAR DATA LINK 07/30/82C 46222 F-67 III.A.2.1 EMERGENCY PLAN UPGRADE TO MEET RULE 05/17/83C 46294 F-68 III.A.2.2 METEOROLOGICAL DATA UPGRADE 12/15/87 46365 F-69 III.D.3.3 IMPLANT RADIATION MONITORING 02/18/82C 46436 F-70 III.D.3.4 CONTROL ROOM HABITABILITY 02/07/82C 56115 F-71 I.D.1.2 DETAILED CONTROL ROOM REVIEN (FDLLONUP TO 07/01/86 49668 G-01 REACTOR COOLANT PUMP TRIP (D660 - II.K.3.5) 08/01/86

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118:

FACILITY IMPLEMENTATION 04/14/86l IRYSTALRIVER3 (CONTINUATION)

FAC NO.

MPA 9 TITLE 9729 B-72

-CRYSTAL RIVER 3 NUREG 0737 TECH SPECS (GENERIC LTR 82-16) 52749 B-76 CRYSTAL RIVER 3 - ITEM 1.1 - POST TRIP REVIEW PROGRAM DESCRIPTION AND PROCEDURES h2830 B-77 CRYSTAL RIVER 3 - ITEM 2.1 - EQUIPMENT CLASSIFICATION AND VENDOR INTERFACE - RTS COMPONENTS

%2911 B-78 CRYSTAL RIVER 3 - ITEMS 3.1.1 & 3.1.2 - POST MAINTENANCE TESTING PROCEDURES / VENDOR RECOMMENDATIONS - RTS COMPONE!

$2992 B-79 CRYSTAL RIVER 3-ITEM 3.1.3 -POST-MAINT TESTING-CHANGES TO TECH SPECS-RTS COMPONENTS p53026 B-80 CRYSTAL RIVER 3-ITEM 4.1 RX TRIP SYSTEM RELIABILITY-VENDOR RELATED MODIFICATIONS h3119 B-81 CRYSTAL RIVER 3 - ITEMS 4.2.1 & 4.2.2 - PREVENTATIVE MAINT PROGRAM FOR REACTOR TRIP BREAKERS - MAINTENANCE & TRENE' h3169 B-82 CRYSTAL RIVER 3 - ITEM 4.3 - AUTDAMTIC ACTUATION OF SHUNT.

TRIP ATTACHMENT FOR H AND B & H PLANTS h4527 B-83. CRYSTAL RIVER 3 - TECHNICAL SPECIFICATIONS COVERED BY GENERIC LETTERS 83-36, 83-37 FOR NUREG-0737 3581 B-85 CRYSTAL RIVER 3 - ITEM 1.2 - POST TRIP REVIEM-DATA AND INFORMATION CAPABILITY i

i 3664 B-86 CRYSTAL RIVER 3 - ITEM 2.2 - EQUIPMENT CLASSIFICATION AND' VENDOR INTERFACE - ALL SR COMPONENTS

. 3747 B-87 CRYSTAL RIVER-ITEMS 3.2.1 & 3.2.2 - POST-MAINT TESTING PROCEDURES AND VENDOR RECOMMENDATIONS - ALL SR COMPONEN!

3830 B-88 CRYSTAL RIVER 3 - ITEM 3.2.3 - POST-MAINTENANCE TESTING

-CHANGES TO TECH. SPEC. - ALL SR COMPONENTS 3906 B-89 CRYSTAL RIVER 3 - ITEMS 4.2.3 & 4.2.4-PREVENTATIVE MAINT.

PROGRAM FOR RX TRIP BREAKERS-LIFE TESTING & REPLACEMENT:

' 5351 B-90 CRYSTAL RIVER 3 - ITEM 4.3(TS) - AUTOMATIC ACTUATION OF SHUNT TRIP FOR H AND B&W PLANTS - TECH SPECS 33953 B-91 CRYSTAL RIVER 3 - ITEM 4.4 - IMPROVEMENTS IN MAINTENANCE AND TEST PROCEDURES FOR B & H PLANTS l 4057 B-92 CRYSTAL RIVER 3 - ITEM 4.5.1 - REACTOR SYSTEM FUNCTIONAL TESTING - DIVERSE TRIP FEATURES

$3974 B-93 CRYSTAL RIVER 3 - ITEMS 4.5.2 & 4.5.3 - REACTOR TRIP SYSTEM FUNCTIONAL TESTING - ALTERNATIVES & TEST INTERVA:

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117 FACILITY IMPLEMENTATION 04/14/86 CRYSTAL RIVER 3 (CONTINUATION)

'AC NO.

MPA 8 TITLE I45619 F-47 CRYSTAL RIVER 3 - NUREG-0737 II.K.3.17, ECC SYSTEM OUTAGES 112743 B-48 CRYSTAL RIVER 3 - ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEM VOLTAGE I43076 B-52 CRYSTAL RIVER 3 - REVIEW OF SAFETY ASPECTS OF INADVERTENT SI DURING SURVEILLANCE TESTING I42121 B-57 CRYSTAL RIVER 3 - DECAY HEAT REMOVAL CAPABILITY TECH SPECS 145815 F-57 CRYSTAL RIVER 3 - NUREG-0737 II.K.3.30. SB LOCA OUTLINE 148156 F-58 CRYSTAL RIVER 3 -NUREG 0737 II.K.3.31 COMPLIANCE HITH 10 CFR 50.46 142902 B-59 CRYSTAL RIVER 3 - MASONRY HALL DESIGN. RESPONSE TO IE BULLETIN 80-11 142512 B-60 CRYSTAL RIVER 3 - ENVIRONMENTAL QUALIFICATION OF SAFETY RELATED ELECTRICAL EQUIPMENT (80-CLI-21) 142664 B-61 CRYSTAL RIVER 3 - IE BULLETIN 79-27, LOSS OF NON CLASS IE INST & CONTR. P0HER. REV. & EVAL. RESPONSES 142734 B-62 CRYSTAL RIVER 3 - ESF RESET CONTROL DESIGN DEFICIENCY

- I8E BULLETIN 80-06 143912 B-63 CRYSTAL RIVER 3 - STATION BLACKOUT PROCEDURES

& TRAINING 145935 F-63 CRYSTAL RIVER 3 - NUREG-0737 III.A.1.2, TECHNICAL SUPPORT CENTER 146006 F-64 CRYSTAL RIVER 3 - NUREG-0737 III.A.1.2, OPERATIONAL SUPPORT CENTER 143263 B-64 CRYSTAL RIVER 3 - BSH ACCIDENT INDUCED NEUTRON FLUX ERRORS (MULTI-PLANT ITEM B-64) 146078 F-65 CRYSTAL RIVER 3 - NUREG-0737 III.A.1.2, EMERGENCY OPERATIONS FACILITY I47166 B-66 CRYSTAL RIVER 3 NATURAL CIRCULATION C00LDOHN (GENERIC LTR 81-21) 146150 F-66 CRYSTAL RIVER 3 - III.A.2 NUCLEAR DATA LINK DATA 146222 F-67 NUREG-0737, III.A.2.1, EMERGENCY PLAN UPGRADE TO MEET RULE 146294 F-68 CRYSTAL RIVER 3 - NUREG-0737 III. A.2.2, METEOROLOGICAL DATA UPGRADE 146305 F-69 CRYSTAL RIVER 3 - NUREG-0737 III.D.3.3, INPLANT RADIATION MONITORING 146831 B-69 CRYSTAL RIVER 3 - PHR MSLB HITH CONTD FEEDHATER ADDITION I46436 F-70 CRYSTAL RIVER 3 - NUREG-0737 III.D.3.4, CONTROL ROOM HABITABILITY 156115' F-71 CRYSTAL RIVER 3 - I.D.1.2 DETAILED CONTROL ROOM DESIGN REVIEW

SUMMARY

REPORT - F-71 e

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RYSTAL RIVER 3 (CONTINUATION)

'AC NO.

MPA 4 TITLE 145435 F-39 CRYSTAL RIVER 3 - NUREG-0737 II.K.3.5, AUTO TRIP OF RCPS 108702 B-39 CRYSTAL RIVER 3 - PHR PRESSURE-TEMPERATURE TECH SPECS 111109 B-41 CRYSTAL RIVER 3 - FIRE PROTECTION SER SUPPLEMENT 111861 B-42 CRYSTAL RIVER 3 - TMI FOLLOHUP 111796 B-43 CRYSTAL RIVER 3 - FEEDHATER LINE CRACKS 112451 B-44 CRYSTAL RIVER 3 - LESSONS LEARNED IMPLEMENTATION 130626 B-44 CRYSTAL RIVER-2.1.7.B CONTROL GRADE AUX FEED FLOH INDICATION 130627 B-44 CRYSTAL RIVER-2.1.5 A,C DEDICATED H2 CONTROL PENETRATIONS & RECOMBINER PROCEDURE 130628 B-44 CRYSTAL RIVER-2.1.1. EMER. POWER SUPPLY PORV/

BLOCK VALVE, PER HEATER & LEVEL 130629 B-44 CRYSTAL RIVER-2.2.2 A,B,C CONTROL ROOM ACCESS, TSC, OPERATIONAL SUPPORT CENTER 430630 B-44 CRYSTAL RIVER-2.2.1 A,B,C SHIFT SUPER. RESP.,

STA, TURNOVER PROCEDURES 130631 B-44 CRYSTAL RIVER-2.1.8.C IMPROVED IODINE INST.

130632 B-44 CRYSTAL RIVER-2.1.8.B HIGH RANGE RADIATION MONITORS 430633 B-44 CRYSTAL RIVER-2.1.8.A POST ACCIDENT SAMPLING 130634 B-44 CRYSTAL RIVER-2.1.6.B SHIELDING REVIEH 130635 B-44 CRYSTAL RIVER-2.1.6.A SYSTEMS INTEGRITY FOR HIGH RADI0 ACTIVITY 130636 B-44 CRYSTAL RIVER-2.1.4 DIVERSE CONTAINMENT ISOLATION 130657 B-44 CRYSTAL RIVER-2.1.3.B INST. FOR CORE COOLING 130638 B-44 CRYSTAL RIVER-2.1.3.A DIRECT INDICATION OF VALVE POSITION 130639 B-44 CRYSTAL RIVER-2.1.2 RELIEF & SAFETY VALVE TESTING 112883 B-45 CRYSTAL RIVER 3 - PRIMARY COOLANT SYSTEM PRESSURE ISOLATION VALVES 112599 B-46 CRYSTAL RIVER 3 - ANALYSIS OF TURBINE DISC CRACKS 112731' B-47 CRYSTAL RIVER 3-ECCS CLAD SHELLING & RUPTURE

t-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO.

115 FACILITY IMPLEMENTATION 04/14/86 lRYSTAL RIVER 3 (CONTINUATION)

'AC NO.

MPA 9 TITLE 159949 A-21 CRYSTAL RIVER 3 - 10CFR50.61 PRESSURIZED THERMAL SHOCK RULE REQUIREMENTS, PHASE 1 108883 B-22 CRYSTAL RIVER 3 - MECHANICAL SNUBBERS 145053 F-22 CRYSTAL RIVER 3 - NUREG-0737 II.F.1.3, CONTAINMENT HIGH RANGE MONITOR 147590 F-23 CRYSTAL RIVER 3 - NUREG 0737 ITEM II F1.4 - CONTAINMENT PRESSURE INSTRUMENT 110017 B-23 CRYSTAL RIVER 3 - POTENTIAL EQUIPMENT FAILURES SYSTEM COMPLETE (TASK G) 14259G B-24 CRYSTAL RIVER 3 - LONG TERM REVIEW CONTAINMENT PURGE AND VENT (B-24) 110211 B-24 CRYSTAL RIVER 3 - CONTAINMENT PURGE 147661 F-24 CRYSTAL RIVER 3 - NUREG 0737 ITEM II F1.5 CONTAINMENT HATER LEVEL MONITOR l

147732 F-25 CRYSTAL RIVER 3 - NUREG 0737 ITEM II F1.6 CONTAINMENT HYDROGEN MONITOR l

110254 B-26 CRYSTAL RIVER 3 - INADVERTENT SAFETY INJECTION DURING C00LDOHN (PHR'S) 5124 F-26 CRYSTAL RIVER 3 - NUREG-0737 II.F.2.3, INADEQUATE CORE COOLING INSTRUMENTATION 2792 F-27 CRYSTAL RIVER 3 - CONFIRMATORY ORDER - ICS RELIABILITY ANALYSIS 5183 F-28 CRYSTAL RIVER 3 - NUREG-0737 II.K.2.10, SAFETY GRADE ARTS 5190 F-29 CRYSTAL RIVER 3 - NUREG-0737 II.K.2.11, OPERATOR TRAINING AND DRILLING

-3426 F-30 CRYSTAL RIVER 3 - ITEM II K.2.13 THERMAL-MECH EFFECTS OF HPI ON VESSEL

'5197 F-30 CRYSTAL RIVER 3 - NUREG-0737 II.K.2.13, THERMAL-MECHANICAL REPORT 5204 F-31 CRYSTAL RIVER 3 - NUREG-0737 II.K.2.14, LIFT FREQUENCY OF PORV'S AND SV'S 5211 F-32 CRYSTAL RIVER 3 nUREG-0737 II.K.2.16, RCP SEAL DAMAGE 5217 F-33 CRYSTAL RIVER 3 - NUREG-0737 II.K.2.17, POTENTIAL FOR VOIDING IN RCS 5223 F-35 CRYSTAL RIVER 3 - NUREG-0737 II.K.2.20, SYSTEM RESPONSE TO SB LOCA 5268 F-36 CRYSTAL RIVER 3 - NUREG-0737 II.K.3.1, AUTO PORV ISOLATION 5314 F-37 CRYSTAL RIVER 3 - NUREG-0737 II.K.3.2, REPORT ON PORV FAILURES 5333' F-38 CRYSTAL RIVER 3 - NUREG-0737 II.K.3.3, REPORT ON RV/SV FAILURES l

l

t-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE NO lit; FACILITY IMPLEMENTATION 04/14/8tv t

RYSTAL RIVER 3 (CONTINUATION) s FAC NO.

MPA 9 TITLE i

112321 D-15 CRYSTAL RIVER 3 - HELB AND CONSEQUENTIAL SYSTEM FAILURE CRYSTAL RIVER 3 144668 F-15 CRYSTAL RIVER 3 - NUREG-0737 II.E.1.1, AFH SYSTEM EVALUATION 112561 A-15 CRYSTAL RIVER 3-QUALITY ASSURANCE REQUIREMENTS REGARDING DIESEL GENERATOR FUEL DIL 152220 C-15 CRYSTAL RIVER 3 - CONTROL OF HEAVY LOADS - PHASE II (FOLLONUP OF MPASC-10) 147555 A-16 CRYSTAL RIVER, QUALIFICATIONS: INSP, EXAM, TEST AUDIT PERSONNEL 158054 C-16 CRYSTAL RIVER 3-UTILITY RESPONSES TO STAFF RECOMMENDATIONS CONCERNING STEAM GENERATORS (GL 85-02) 144708 F-16 CRYSTAL RIU5R 3 - NUREG-0737 II.E.1.2.1, AFH SAFETY GRADE AUTO INITIATION

$44750 F-17 CRYSTAL RIVER 3 - NUREG-0737 II.E.1.2.2, AFH SAFETY GRADE FLON INDICATION h08881 B-17 CRYSTAL RIVER 3 - HYDRAULIC SNUBBERS i

b46559 D-17 CRYSTAL RIVER 3 - DEFINITION OF OPERABILITY h33037 D-17 CRYSTAL RIVER 3 - TECHNICAL SPECIFICATIONS DEFINING OPERABILITY FOR SAFETY SYSTEMS 51083 A-17 CRYSTAL RIVER 3 - INSTRUMENTATION TO FOLLOW THE COURSE OF AN ACCIDENT (RG 1.97)

E51734 D-18 CRYSTAL RIVER 3 - NUREG-0630' CLADDING MODELS FOR LOCA ANALYSIS i

I

.l 04769 F-18 CRYSTAL RIVER 3 - NUREG-0737 II.E.4.1.2, DEDICATED HYDROGEN PENETRATIONS 107556 B-18 CRYSTAL RIVER UNIT 3-REVIEW DECAY HEAT PUMP SHAFT FAILURES I 5703 A-18 CRYSTAL RIVER 3 - TECH. SPECS. AFFECTED BY 50.72 AND 50.73 (GL 83-43) 55851 D-19 CRYSTAL RIVER 3 - DIESEL GENERATOR RELIABILITY TECH.

SPECS. (GL 84-15) 4840 F-19 CRYSTAL RIVER 3 - NUREG-0737 II.E.4.2, CONTAINMENT ISOLATION DEPENDABILITY

$9085 A-20 CRYSTAL RIVER 3 - 10CFR50.62 OPERATING REACTOR REVIENS h10317 B-20 CRYSTAL RIVER 3 - CONTAINMENT LEAKAGE DUE TO SEAT DETERIORATION h04911 F-20 CRYSTAL RIVER 3 - NUREG-0737 II.F.1.1, NOBLE GAS MONITOR

'4982 F-21 CRYSTAL RIVER 3 - NUREG-0737 II.F.1.2, IODINE /

PARTICULATE SAMPLING J10379

  • B-21 CRYSTAL RIVER 3 - LOSS OF 125V DC BUS VOLTAGE HITH LOSS OF ANNUNCIATOR SYSTEM r

v.

-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE N0.8 113-FACILITY IMPLEMENTATION 04/14/86i

'RYSTAL RIVER 3 (CONTINUATION)

I I

rAC NO.

MPA 9 TITLE 07056 D-08 CRYSTAL RIVER 3 - DELETE USE OF SODIUM THIOSULFATE l

h08606 D-08 CRYSTAL RIVER 3 - REACTOR BUILDING S.'AY SYSTEM h1153 F-08 CRYSTAL RIVER 3 - I.D.1.11 - DETAILED CONTROL ROOM DESIGN REVIEH PROGRAM PLAN F-08

)51233 F-09 CRYSTAL RIVER 3 - I.D.2. SAFETY PARAMETER DISPLAY SYSTEM 11378 A-09 CRYSTAL RIVER 3-REACTOR VESSEL BELTLINE MATERIAL SURVEILLANCE 10729 A-10 CRYSTAL RIVER 3 - CONTINGENCY PLAN REVIEW j07469 B-10 CRYSTAL RIVER 3--POISDN ROD ASSEMBLY FAILURE REVIEH I

h D-10 CRYSTAL RIVER 3 - REVIEN OF ASYMMCTRIC LOCA LOADS SUBMITTAL (08843

'07983 C-10 CRYSTAL RIVER 3-CNTRL OF HEAVY LOADS OVER SPENT FUEL POOL (NUREG 0612) 44363 F-10 CRYSTAL RIVER 3 - NUREG-0737 II.B.1, RCS HIGH POINT VENTS h0733 A-11 CRYSTAL RIVER 3 - GUARD TRAINING PLAN REVIEN 10103 D-11 CRYSTAL RIVER 3 - ENHANCED FISSION PRODUCT RELEASE FOR HIGH BURNUP LHR FUEL 7929 F-11 CRYSTAL RIVER 3 - PLANT SHIELDING MODIFICATIONS (II.B.2.2) 10731 A-12 CRYSTAL RIVER 3 - VITAL AREA ANALYSIS 44431 F-12 CRYSTAL RIVER 3 - NUREG-0737 II.B.3.2, POST ACCIDENT SAMPLING MODIFICATIONS 44501 F-13 CRYSTAL RIVER 3 - NUREG-0737 II.B.4.1, TRAINING FOR MITIGATING CORE

08006 D-13 CRYSTAL RIVER 3 - SMALL BREAK ECCS ERROR (B&H)

I'08884 D-14 CRYSTAL RIVER 3 - REACTOR VESSEL ATYPICAL HELD MATERIAL 10845 B-14 CRYSTAL RIVER 3 - CONTROL R0D GUIDE TUBE HEAR 11007 D-14 CRYSTAL RIVER 3-REVISF) P-T CURVES-ATYPICAL HELD 4571 F-14 CRYSTAL RIVER 3 - RV AND SV TESTING I

0454 A-14 CRYSTAL RIVER 3 - REVIEW REQUEST FOR RELIEF FROM ASME SEC. XI PUMP & VALVE TESTING REQUIREMENTS 3647

  • C-14 CRYSTAL RIVER 3 - SEISMIC QUALIFICATION OF THE AUXILIARY FEEDHATER SYSTEM 4

4

1-1208731-001 REGULAT0RY INF0RMATION TRACKING SYSTEM PAGE N0.8 118 FACILITY IMPLEMENTATION 04/14/86 2ACILITY: CRYSTAL RIVER 3

'LANT LOCATION: 7 MI NH OF CRYSTAL RIVER, FLA LICENSED POWER: 2544 MHT PROJECT MANAGER: H. SILVER 10CKET NUMBEP.:

050-00302 DESIGN P0HER:

0825 MHE BRANCH CHIEF:

J. STOLZ ARCH / ENGINEER: GIL NSSS VENDOR:

B&W LIC. ASSISTANT:

R. INGRAM LE INSPECTOR:

T. STETKA FAC NO.

MPA 9 TITLE 144012 F-01 CRYSTAL RIVER 3 - NUREG-0737 I.A.1.1 STA LONG TERM REQUIREMENTS 108889 C-01 CRYSTAL RIVER 3 - SECONDARY CHEMISTRY BASIS 104548 A-01 CRYSTAL RIVER 3 - REVIEN REQUEST FOR HAIVER OF CERTAIN REQUIEMENTS OF ASME SEC. XI CODE ON INSERVICE INSPECTION 107468 E-01 CRYSTAL RIVER 3 - SPENT FUEL POOL MODIFICATION 149668 G-01 CRYSTAL RIVER 3 - REACTOR COOLANT PUMP TRIP 110907 A-02 CRYSTAL RIVER 3--APPENDIX I TECH SPEC IMPLEMENTATION 108985 A-02 CRYSTAL RIVER 3 - APPENDIX I REVIEH 144080 F-02 CRYSTAL RIVER 3 - NUREG-0737 I.A.1.3.1, SHIFT MANNING OVERTIME LIMITS 107189 B-02 REVIEH FIRE PROTECTION PP.0 GRAM - CRYSTAL RIVER 3 107065 A-03 CRYSTAL RIVER 3 - PHYSICAL SECURITY PROGRAM 108377 B-03 CRYSTAL RIVER 3 - PHR MODERATOR DILUTION 111296 E-03 CRYSTAL RIVER 3-RELOAD FOR CYCLE 2 144151 F-03 CRYSTAL RIVER 3 - HUREG-0737 I.A.2.1.4, UPGRADING OF RO AND SRO TRAINING 144222 F-04 CRYSTAL RIVER 3 - NUREG-0737 I.C.1.2.A, INADEQUATE CORE COOLING GUIDELINES 106720 B-04 CRYSTAL RIVER 3 - REACTOR VESSEL OVERPRESSURE PROTECTION 144292 F-05 CRYSTAL RIVER 3 - PROCEDURES GENERATION PACKAGE REVIEH (NUREG 0737 SUPP/1) 147205 F-06 CRYSTAL RIVER 3 - FEEDBACK OF OPERATING EXPERIENCE (AP I.C.5) 108880 C-06 CRYSTAL RIVER 3 - PHR PUMP & S/G SUPPORTS - LAMELLAR TEARING & FRACTURE TOUGHNESS 108882 C-07 CRYSTAL RIVER 3 - FUEL HANDLING ACCIDENT INSIDE CONTAINMENT 147277' F-07 CRYSTAL RIVER 3 - CORRECT PERFORMANCE OF OPERATING ACTIVITIES (API.C.6) 4 9

.