ML20151S867
| ML20151S867 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 08/09/1988 |
| From: | Moran D NRC OFFICE OF SPECIAL PROJECTS |
| To: | NRC OFFICE OF SPECIAL PROJECTS |
| References | |
| NUDOCS 8808160141 | |
| Download: ML20151S867 (28) | |
Text
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- e p asiuq'og UNITED STATES 8 n NUCLEAR REGULATORY COMMISSION
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$ $ WASHINGTON, D. C. 20555
%*0ocketNos.50-260 E
1.ICENSEE: Tennessee Valley Authority FACILITY: Browns Ferry Nuclear Plant, Unit 2
SUBJECT:
OSP/TVA MEETING ON FUEL LOAD ISSUES AND POWER ASCENSION TESTING AT BROWNS FERRY NUCLEAR (BFN) POWER, STATION, UNIT 2. JULY 7, 1988 The subject meeting began at 9:00 a.m. and ended at 12:30 p.m. in the BFN Administration Building "War Room" at the Browns Ferry Nuclear Plant site.
The purpose of the meeting was to discuss fuel load issues and BFN's power ascension plans. The agenda and attendance list are included as Enclosures 1 and 2 respectively. Twenty-one viewgraphs were used at the meeting (Enclosure 3).
The Manager of Licensing stated the objective for the meeting as follows.
TVA would describe their plans and explain the prerequisites for fuel reload and power ascension testing and ask the NRC for its concurrence.
The level 1 schedule (Enclosure 4) was reviewed by the TVA Restart Director.
The status of each line item was discussed as to degree of completion as of the current week and forecast completion at time of scheduled fuel reloading. In general, where provided by TVA each line item or task was discussed in terms of discovery, design and implementation (installation). Enclosure 4 is annotated as to the percentage completion of the implementation of tasks as of the date for this meeting "Timt. Now" line and forecast completion at the fuel reload schedule date "Reload Core" line.
During the discussion of the schedule status and forecast, TVA pointed out critical items on their schedule. These included:
A 95% inspection by the NRC for Appendix R is scheduled for October 1,1988 See line marked "B", Appendix R Task, Enclosure 4.
The ampacity task is to continue through the month of October 1988. See line marked "D" Electrical Issues, Enclosure 4.
The Drywell fire repair and replacement is on the critical path. Maintenance Requests (MR) closures are running 250/we .k now. Test Director stated TVA may need to increase closures to 450/ week in order to meet the operability point, so operaters can move in. The Plant Manager stated that "work control" has been the most difficult area to improve. He pointed out that the maintenance improvement program was established in recognition of tnis.
The Materials Task, see line marked "N" (Enclosure 4) is on schedule and will be essentially 100% implemented at fuel reload.
8808160141 880809 PDR ADOCK 05000260 P PNU \
t The Licensing Task, seo line marked "0" (Enclosure 4), was summed up by the Licensing Manager as follows:
- NRC has 31 Safety Evaluations (SE) in process.
- According to the current schedule, 20 SEs will be in process at fuel reload.
- TVA has 20 submittals for the NRC in preparation.
- Concerning Technical Specification Changes.
- 16 are in process
- 8 additional are to be initiated of which 6 will be transmitted to NRC in July 1988 The staff made two points concerning the viability of the restart effort:
System function and operability must be clearly understood in the sense of technical specification definition in order to judge whether systems are in the proper condition for fuel reload. .
TVA needs to address the question: "Must BFN be prepared for a design basis accident at fuel reload?"
The BFN Return to Service Manager described the return to service process. See , viewgraphs 3 through 8. Highlights of this presentations are:
The System Pre-operability Checklist (SPOC) is used to determine whether the prereauisites for operability of a system are complete. The SP0C is governed by Site Director's Standard Practice (SDSP) procedure 12.7.
The Operational Control of Systems was described by the BFN Operations Superintendent. See viewgraphs 9 through 11. Highlights of this presentation are:
Viewgraph 9, "Fuel Load Systems Requirements" lists all the systems covered by Technical Specifications necessary for fuel reload - The Master List.
Viewgraph 9 lists component parts of the systems configuration portion of operations control. A significant detail was brought out concerning the physical processing of drawings. Taere are approximately 1600 drawings.
There will be about 100 people updating these drawings. This operation includes a drawing check function and there is a chief checker sign off in the title block.
The Restart Test Program and the plans for power ascension testing were explained by the BFN Restart Test Manager. Viewgraphs 13 through 21 were used in this presentation. Highlights of this presentation are:
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Restart Test Program Status - refer to viewgraph 14.
All test specifications are approved - a total of 41; and all test procedures are approved - a total of 43.
Of the 16 tests conducted to date, 6 were for fuel ~oad; of the 16 tests now l in progress, 12 are for fuel load. I The loss of power / loss-of-coolant accident "C" test is scheduled to be re-run July 23 and 24,1988.
Restart Test Program (RTP) Test Exceptions - refer to viewgraph 15. l This is an accounting of the categories of test exceptions and the i totals - RTP overall and those still open.
Restart Test Performance Schedule - refer to viewgraph 16.
l These are ;he significant milestone including completion of power ascension l testing in February 1989. These dates are based on schedules current at i the time of this meeting.
l Appendix A - refer to viewgraph 20. BFN will use an auxiliary boiler (250 i psi capability) during these tests t3 appropriate. This boiler is low ;
capacity but will provide full flow - not full pressure for the reactor. i This program includes a low power and a high power scram.
Power Ascension Milestone Chart - refer to viewgraph 21.
l This chart describes the power ascension test plan in terms of percent !
power vs test plateaus.
It was decided by the staff that a letter is to be transmitted to TVA (issued ;
7/28/88) stating in general that fuel reload and power ascension must be I accomplished on operable systems as prescribed by the applicable technical specification.
Original Signed by Gerald E. Gears for David H. Moran, Project Mana n c TVA Projects Division Office of Special Projects
Enclosures:
As stated cc w/ enclosures See next page Distribution Docket File Those on Attached List NRC PDR Local PDR 0 VA/LA OLP'T,4/PM Ofk M /
M 1/ GWrf Wp kr 8 88 8/J /E8 81 8 8/ 88 ae-- t-c -- + +--
Browns Ferry Nuclear Plant Uhits 1, 2, and 3 cc:
General Counsel Regional Administrator, Region II Tennessee Valley Authority U.S. Nuclear Regulatory Commission 400 West Summit Hill Drive 101 Marietta Street, N.W.
E11 B33 Atlanta, Georgia 30323 Knoxville, Tennessee 37902 Resident Inspector / Browns Ferry NP Mr. R. L. Gridley U.S. Nuclear Regulatory Commission Tennessee Valley Authority Route 12, Box 637 SN 1578 Lookout Place Athens, Alabama 35611 Chattanooga, Tennessee 37402-2801 Dr. Henry Myers, Science Advisor Mr. H. P. Ponrehn Committee on Interior Tennessee Valley Authority and Insular Affairs Browns Ferry Nuclear Plant U.S. House of Representatives P.O. Box 2000 Washington, D.C. 20515 Decatur, Alabama 35602 Tennessee Valley Authority Mr. M. J. May Rockville Office Tennessee Valley Authority 11921 Rockville Pike .
Browns Ferry Nuclear Plant Suite 402 P.O. Box 2000 Rockville, Maryland 20852 Decatur, Alabama 35602 Mr. D. L. Williams Mr. S. A. White Tennessee Valley Authority Senior Vice President, Nuclear Group 400 West Summit Hill Drive Tennessee Valley Authority W10 885 6N 38A Lookout Place Knoxville, Tennessee 37902 1101 Market Street Chattanooga, Tennessee 37402-2801 Chairman, Limestone County Commission P.O. Box 188 Athens, Alabama 35611 Claude Earl Fox, M.D.
State Health Officer State Departnent of Public Health State Office Building Montgomery, Alabama 36130 l
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Enclosure 1 AGENDA FOR OSP/TVA MEETING ON FUEL LOAD ISSUES AND POWER ASCENSION TESTING TUESDAY 9 A.M. TO 12 NOON, JULY 7, 1988 I. Over ew John Walker Plant Manager II. Level I Schedule Terry Valenzano Restart Director III. Return to Service Process Rick Wall Return to Service Manager IV. Operational Control of Systems Bob McKeen. l Operations Superintendent V. Restart Test Program and Don Hosmer Power Ascension Testing Restart Test Manager e
VI. Actions NRC/TVA All. .. _u - .
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Enclosure 2 ATTENDANCE LIST July 7, 1988 TVA NRC S. A. White J. Partlow J. R. Bynum S. Black J. A. Kirkebo F. McCoy C. C. Mason D. Moran R. L. Gridley R. Pierson T. C. Valenzano J. Carpenter J. G. Walker M. Branch R. McKeon
- C. Brooks D. Hosmer W. Little P. J. Polk P. Speidel R. E. Young G. G. Turner R. Wall H. J. Hay ,
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i FUEL LOAD ISSUES AND POWER -
ASCENSION TESTING -
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- 1. OVERVIEW
- 11. LEVEL i SCHEDULE l 111. RETURN TO SERVICE PROCESS
!' IV. OPERATIONAL CONTROL OF SYSTEMS l-l- V. RESTART TEST PROGRAM AND POWER ASCENSION TESTING l
l VI. NRC/TVA ACTIONS 4
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l NRC/TVA MEETING - JULY 7,1988 OVERVIEW s SCHEDULE STATUS REVIEW l
= SYSTEM RETURN TO SERVICE I
- TR ANSITION - M AJOR PROGR AMS/ SYSTEM COMPLETION
- IDENTIFY SYSTEMS REOUIRED TO SUPPORT E ACH MILESTONE
- IDENTIFY WORK REOUIRED ON EACH SYSTEM TO SUPPORT MIL E STO N E S 1
- M AINTAIN CONTROL OF SYSTEM CONFIGUR ATION AND STATUS 4
= RESTART TES T PROGR AM/ POWER ASCENSION TESTING
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SITE MASTER PUNCHLIST
= TRANSITION TO SYSTEM APPROACH
- CONSOLIDATE OPEN RESTART ITEMS FROM INDIVIDUAL DATA BASES
= SYSTEM ENGINEER / OPERATORS CODE OPEN ITEMS
= SYSTEM SCHEDULE DEVELOPED j
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= GOVERNED BY A FROCEDURE - SDSP 12.7
= COMPREHENSIVE CHECKLIST
= INPUT FROM SMPL
= USED BY OPERATIONS TO ENSURE PREREQUISITES FOR OPERABILITY ARE COMPLETE 4
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SITE _hiASTE] L P l I N C11 LIST _(S M PL)_D E biC R I ET10N TROI x o CAQlfs 'x -
o CATD"S \ SI Scheduling & Tracking o NSRS Items o NSRH lierns
\ " SI's o NhlRG lleins o ISEG lleins / 7 klR Tracking o ANI Iteins N'd / ,/ 0 AllE3 l' /
o INPO llenis g____._
o SCirs/ Calfs /Dirs l' TACP Tracking o pjges SMPL <y o TACrs CCTs
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o NRC Inspection lleins o 1.Elrs '
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Authorized Nuciaar Insp2ctor CALCS- Calculations CAQRs Conditions Adverse to Quality Reports CARS Corrective Action Reports CATDs Corrective Action Tracking Documents (Employee Concerns)
CCTS Corporate Commitment Tracking System DCNs Design Change Notices DCRs Design Change Requests DRs Discrepancy Reports ECNa Engineering Change Notices EQ Environmental Qualification I&E Inspection and Enforcement INPO Institute of Nuclear Power Operations e
ISEG Independent Safety Engineering Group LERs Licensee Event Reports MOD Modification MRs Maintenance Requests NMRG Nuclear Managers Review Group NRC Nuclear Regulatory Ccmmission NSRB Nuclear Safety Revies Board NSRS Nuclear Safety Review Staff PIRs Problem Identification Reports PMs Preventive Maintenance SCRs Significant Condition Reports sis Surveillance Instructions SMPL Site Master Punchlist TACFs Temporary Alteration Control Forms TROI Tracking and Reporting of Open Items !
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FUEL LOAD SYSTEM REQUIREMENTS 57 AUX. ELEC. (COLD S/D) 433 TORUS (LEVEL & TEMP.)
64 REACTOR BLDG. VE NT. 23 RHRSW (RHR SUPPORT) 64 SECONDARY CONTAINMENT 74 RHR (1 LOOP, 3 PUMPS) 67 EECW (D/G, RHR, CS) 75 CORE SPR AY (1 LOOP) 82 STANDBY D/G 63 STANDBY LlOUlO CONT.
65 SBGT 99 RPS/PRIS/RMCS 31 CONTROL BAY H/V 92 NEUTRON MONITORING 69 RWCU 90 RAD MON. (RFF & PART RB) 03 FW (LEVEL INSTR.) 79 FUEL HANDLING 85 CRD 84 CAD (CAM /H202 MON.)
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- OPERATIONAL CONTROL OF SYSTEMS -
j SYSTEM PRE-OPERABILITY CHECKLIST (SPOC) l l~ PART IX - SYSTEM CONFIGURATION l
! CLEARANCES I SYSTEM WALKDOWN I LABELING VALVE CHECKLIST FANEL CHECKLIST
- i ELECTRICAL CHECKLIST i INSTRUMENT CHECKLIST SYSTEM STATUS FILE UPDATED STATUS BOARD UPDATED LOGS ARE ADEQUATE
! DRAWINGS ARE LEGIBLE AND AVAILABLE
! PERFORM REQUIRED SURVEILLANCE TEST i
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OPERATIONAL CONTROL OF SYSTEMS MAINTAIN CONTROL OF SYSTEM COMPONENTS l = SRO's IN PLANNING, 24HR REVIEW
= OPERATIONS CONTROL CENTER
= COMPONENTS ARE POSITIONED IN ACCORDANCE WITH ,
APPROVED PLANT PROCEDURES i
DOCUMENTING ABNORMAL STATUS OF COMPONENTS i a CLEARANCE PROCEDURE
= TACF's REVIEWS i = WEEKLY REVIEW OF SYSTEM STATUS FILE i
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RESTART TEST PROGRAM STATUS OF RESTART TEST PROGRAM (RTP)
= PROGRAM STATUS
= TESTING RESULTS SCHEDULE FOR COMPLETION FOR RTP INTEGRATED COLD FUNCTIONAL TESTING
= PURPOSE
= SCOPE
= SCHEDULE PO% JR ASCENSION TESTING
= INTRODUCTION $
=
REFUELING TEST PROGRAM
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RESTART TEST PROGRAM
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MASTER REFUELING TEST INSTRUCTION
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POWER ASCENSION TEST MATRIX
= RESTART TEST DESCRIPTION -
= TESTING
SUMMARY
SCHEDULE k
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l RESTART TEST PROGRAM STATUS l
41/41 TEST SPECIFICATIONS APPROVED ,
l 43/43 TEST PROCEDURES APPROV!dD l 16 TESTS CONDUCTED (6 FOR FUEL LOAD) !
16 TESTS IN PROGRESS (12 FOR FUEL LOAD) 7 JOINT TEST GROUP APPROVALS OF TEST RESULTS I
22/45 SYSTEM CHECKLISTS COMPLETE 4
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RTP TEST EXCEPTIONS TEST EXCEPTION CATEGORY OPEN TOTAL ,
l l EQUIPMENT MALFUNCTION 22 59 1
EQUIPMENT DID NOT MEET 13 35 PERFORMANCE CRITERIA ,
PLANT /EQUlFMENT AVAILABILITY 17 95 PREREQUISITE /L TIAL CONDITIONS 9 39 j I
ADMINISTR ATIV E 24 141 I
l PERSONNEL 5 25 CAllBR ATION DEFICIENCIES 2 8 .
I OTHER 19 39 I TOTAL 111 441 i
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J RESTART TEST PERFORMANCE SCHEDULE .
FUEL LOAD 09/01/88 RPV HYDRO 10/04/88 PULL CONDENSER VACUUM 09/07/88 BOP SYSTEM IN SERVICE 10/06/88 STARTUP PREPARATIONS COMPLETE 11/21/8 8 CLOSE GENERATOR BREAKER 11/30/88 LOSS OF OFFSITE POWER (PLANNED SCRAM) 12/17/88
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POWER ASCENSION TESTING COMPLETE 02/03/89 W
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REACTOR HYDRO 10/3 :
REACTOR SYSTEMS INTEGRATED FUNCTIONAL 10/24 TU R 3lh E SYSTEUS l\TEG RA- EJ rU \lCT O N A'_ '
COMPLETE CONDEllSER TUBE REPL O Q 10/3
<W WA TURBINE SYSTEMS INTEqtATED FUtJCTIONAL
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- Power Ascension Page 3 ef 4
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l TABLE I POWER ASCENSION TET,T
SUMMARY
MATRIX OPEN IISI TEST NAME VESSEL Heatvo-55% 55-100%
TI 3 TULL CORE LOAD X TI 115 TULL CORE SDM X TI 20 CRD X X TI 12 ROD SEQUENCE EXCHANGE X SI 4.2.C-3 IRM X SI 4.1.B-3 LPRM CAL X X TI 136 APRM (CONSTANT HEATUP) X SI 44B-2 APRM CAL X X TI 135 PROCESS COMPUTER X X
- RTP/PA RCIC X X 071
- RTP/PA HPCI X X 073
- RTP/PA- WATER LEVEL X
- WLM MEASUREMENTS
- RTP/PA SYSTEM EXPANSION X EXP TI 137 CORE POWER DIST X X SI 2.1 CORE THERMAL LIMITS X X TI 130 PRESSURE REGULATOR X X TI 131&
TEEDWATER TUNING X X 132 l l
- RTP/PA- TURBINE TRIP X WITHIN BYPASS CAPACITY
- RTP/PA- TURBINE TRIP TGT X )
- P/PA C00LDOWN OUTSIDE X RSD CONTROL ROOM
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TI 133 RECIRCULATION X X X 134 SYSTEM TUNING (RUNBACL,
- RTP/PA- RECIRCULATION X l RPT FUMP TRIP RTP/PA- LOSS OF OTTSITE X LOP POWER, TURBINE TRIP i TI 82 DRYWELL TEMPER.TURES X X i
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- 1. HIGH PRESSURE COOLANT INJECTION SYSTEM
- 3. WATER LEVEL MEASUREMENT
- 4. THERMAL EXPANSION
- 5. TURBINE TRIP WITHIN BYPASS CAPACITY
- 6. REACTOR FEEDPUMP TRIP .
- 7. TURBINE TRIP / REACTOR SCRAM
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- 8. LOSS OF TURBINE-GENERATOR AND OFFSITE POWER
- 9. RECIRCULATION SYSTEM PERFORMANCE l
- 10. COOLDOWN OUTSIDE THE CONTROL ROOM j l
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SUMMARY
DATED: August 9,1988 Facility: Browns' Firry Nuclear Plant, Unit 2* i DISTRIBUTION c Docket File. l NRC PDR 1 Local PDR l Projects Reading I J. Partlow l S. Richardson i S. Black l B. D. Liaw l D. Moran l G. Gears !
i J. Kelly l M. Sinns .'
l F. McCoy )
J. Rutberg R. Pierson l J. Carpenter M. Branch l C. Brooks l W. Little ,
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