ML20147C085
| ML20147C085 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/01/1987 |
| From: | TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML20147C084 | List: |
| References | |
| FOIA-88-75 NUDOCS 8803020313 | |
| Download: ML20147C085 (301) | |
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II.:T m R E:U E _. NG OUTAG E
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ISSUE DATE DECEMBER 1, 1987
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i ; FIFTH REFUELING OUTAGE EXECUTIVE
SUMMARY
DECEMBER 1, 1987 PAGE NO. - - I OVERVIEV 1 II CURRENT SCHEDULE DEVELOPMENT 2 a) Target Schedule 3-8 b) Highlights 9 - 12 , III SCOPE OF VORK (MAJOR ITEMS) a) Turbine / Generator Activities 13 - 16 b) Fuel Handling /Defueling/ Refueling 17 - 18 c) Inservice Inspection (ISI) 19 - 21 1 d) Integrated Leak Rate Test (ILRT) 22 ,23 e) Plant Modification Activities 24 - 33 f) Corrective and Preventive Maintenance 34 - 35 I IV MANP0'.'ER PROJECTIONS 36 - 40 t V FINANCIAL (PRINCIPAL COST) a) Modification Cost Breakdovn 41 - 50 ] b) Licensing Required / Improvement Modifications
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OVERVIEV Ef forts in preparation for the upcoming Refueling Outage at Davis-Besse Nuclear Fover Station have progressed over the last month. To date the Preliminary Outage Schedule has been completed and distributed to all site groups for their review and comments. Input is still being collected to be resolved / incorporated into the schedule. Currently another activity in the form of the "SYSTEM OF THE DAY" review is in place. This preliminary schedule review provides a forum in which the Outage Management Group and the working level parties, review by system the schedule and logic and identify any concerns. Additionally, veekly Preparation Meetings support requirements such as procedures identification, access control, space allocation, safety and hygiene materials, etc. The Fifth Refueling Outage vill commence on February 15, 1988 and is scheduled to complete by August 15, 1988. The following is a summary of significant areas with changes in target dates of two veeks or greater since the last report: Fuel Handling Activities - The expected submittal of the Reload Report and License Amendment to the NRC has been Rescheduled from December 26, 1987 to February 15, 1988 vhich reflects as a change in an expected NRC approval response from April 25, 1988 to July 15, 1988. ISI Activities - Inspection of the accessible Lover Core Barrel Bolts have been removed from the SR vorkscope. ILRT Activities - The response to RFA 87-778 has rescheduled from November 15, 1987 to November 30. 1987 vhich has delayed revision of DB-PF-03400.4 until late December, 1987. Modification Activities - Currently 134 ($R) modifications (FCR/RFM) are scheduled to be implemented which is a reduction from the 141 modifications previously identified. NCR & PCAO Activities - The completion of Operating Cycle hanger valkdovn NCR and PCAO dispositions has been rescheduled from December 1, 1987 to December 31, 1987. tercettive Maintenance Activities - The completion of the Backlog 3R MVO and vork request review had been rescheduled from December 1, 1987 to December 31, 1987. 1
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, Turbine Generator Activities:
- The issuance of the General Electric Turbine / Generator / Main Feed Pump Turbine Purchase Order 008023S0 in late November, 1987 is a Major Milestone. A Preliminary Vork Schedule has been received from General Electric and draft vork procedures vere reviewed in November, 1987.
The present target for the Turbine Torsional Test is to have General Electric on site January 11, 1988 with testing on January 14 through 17, 1988. Fuel Bandling Activities: Fuel receipt preparation activities, such as the new Radvaste Building door cutout and FCR 83-007 Fuel Handling Bridge Modifications in the Auxiliary Building are in process and receipt is schedulea to start in January, 1988. ISI Activities: Section XI Inservice Inspection and Inservice Test activities have been identified and schedule input regarding these activities is underway. Pressure / hydro tests have been identified as well as ' check and relief valves to be tested. Terformance Engineering has furnished draft copies of 32 test procedures of the approximately fifty required. The remainder vill allev logic tying of all of the Section XI activities. t The only concern regarding ISI activities is related to the Erosion / Corrosion Program. Performance Engineering is evaluating historical data regarding this program ar.d has added approximately forty additional survey parts and is also evaluating techniques to )
- perform UT examinations when the plant is at pover. These issues i need to be resolved by Mid-December to allow final planning for outage related activities. ;
1 j ILRT Activities: RFA 87-778 was expected to be suppliev to Performance Engineering by 9/30/87 to allov revision of DB-PF-03400.4 in October, 1987, 1he RFA response has been delayed to November 30, 1987 with an expect late December, 1987 revision of DB-PF-03400.4. The delays encountered in performing the inventory and ordering of test and pressure equipment for devpoint and flov has resulted in ' a slippage of the ship date. Also considered is the calibration "shelf life" of this instrumer Alon. Due to the ILRT Activity Scheduled 1987. for after Re-fuelita, this ship date is nov December 31, 3 Station Battery: The revrite of station battery specifications (E180) vas completed 1 and approved on August 26, 1987. The purchase order for procurement of the replacement batteries and the battery receipt inspection plan completion dates were not completed on September 15, 1987. However, a Purchase Order is issued nov and the current February 1,1988 delivery of the batteries vill support the outage completion date. + A study is in progress by the Independent Engineering Safety Organization. The results of this study vill be evaluated by Systems and Design Engineering and a DC Load Table vill be developed. This activity is projected to be complete by December 1, 1987 and will not have a direct impact on the SR battery replacement. Snubber Activities: The material for the six 20 inch steam generator snubber rebuilds vas ordered in August as scheduled. The scope of the SR outage snubber vork breaks dovn as follows: 300 snubbers are to be visually inspected, 110 small bore hydraulic snubbers are to be rebuilt due to seven year seal life replacement requirements. Materials for the rebuild have been ordered. There is an on going effort to identify those snubbers that can be replaced non outage under action statements to lessen the outage impact. Also in the scope is the replacement sf i approximately 110 mechanical snubbers with pre-tested, drop-in ; i small bore hydraulic snubbers. A vendor has been selected and material ordering is in progress. MVO generation for the snubber vork is in progress and on schedule. Preventative Maintenance: The completion of the 'PM Standardization Effort' as initially planned was expected to complete by September 15, 1987. However, the scope of the effort has been increased and is nov scheduled to complete by January 1, 1988, which is acceptable. This program vill re-categorire PM's but vall not affect the SR outage PM vorkscope. Presently, 765 PM's are identified as outage related. Approximately 81 PM's require material evaluations by System Engineering and BOM's submitted. The number of manhours estimated for all preventative maintenance for the time frame of December 1, 1987 to May 31, 1988 is approximately 50,000 manhours (appre imately 53 men). Outage PMs have been generated. Maintenance Planning is preparing PMVO packages and forecasts completion by December 31, 1987. Modification A:tivitiest A veekly Engineering Modification Package Reviev Meeting continues to highlight these packages whose agreed upon forecast dates are slipping, for issuance of detail design. 4
.s .
Slipping Packages supporting Control Room Improvement Modifications are of particular concern. Engineered material must be identified as soon as practical in order to obtain needed vendor drawings, manuals and hardware. Dravings and vendor manuals vill provide the needed information for nev instrumentation data packages, test procedure development and maintenance procedure revision. NCR & PCAO Activities: i The NCR and PCAQ's, as they relate to the Outage Licensing Commitments, deal mainly with the hanger review program. These two document types fall into various categories, and are as L follows: NCRs and PCAQs that are draving change only. - This group is the majority of the existing NCRs. NCRs and PCAQs that are in Engineering for disposition, of which Operating Cycle work may result. PCAQs the hanger valkdovn program generates that result in additional Operating Cycle vork. Identified vork items that fall both in the Operating Cycle and the Outage. A.I.R.'s (Additional Information Request), 23 of which are in containment and a growing number of AIR's outside containment that are generated as engineering continues their disposition effort. , All initial hanger valkdovns scheduled for the end of this < i operating cycle have been performed and there subsequent dispositions are scheduled to complete by December 31, 1987. Presently an accelerated effort appears to be required by l engineering if both the dispositions of support deficiencies and Bechtel's operability stress problems are to complete on time. All other initial valkdowns are associated with supports in the control room overhead. These are scheduled to complete during the refueling outage. Also, the two supports on the diesel generator exhaust stacks were inspected during their respective maintenance outage. LCTS Activities: The finalization and qualification of SR LCTS commitments were i completed and presented to the NRC in Mid-November. A scheduled quarterly meeting with the NSC bill continue to refine this list. l I As of this report there are 111 actual 5R LCTS commitments to the j NRC. of which 73 are tied to it.e outage. Close interface between i
)
Planning and Licensing is in progress to assure that all items are addressed and scheduled. These items are planned for completion before the end of the SR outage. Corrective Maintenance Activities: Backlog SR MVO and vork request reviev and evaluation for 3R vork continues towards a December 15, 1987 completion date. Material is being ordered in conjunction with the reviev and preparation of the work packages. All known vork packages required to support SR Outage Activities are targeted to be complete by January 28, 1988, as nov scheduled. Test Procedure Activities: Test review of SR FCR/ MOD's continues as the detailed designs are issued. The development of the 38 identified test procedures (TP's) are in progress. Performance Engineering has hired additional test personnel to assist in writing and implementation of the TP's. Late issue dates for detail design is restraining completion of procedure development. Presently eighteen (5R) TP's are being prepared based on complete design information with one TP approved. 5R Schedule Development: The Preliminary schedule was issued to all site departments on October 28,1987. During the month of November, this schedule issue vas reviewed and some comments vere fed back to Outage Management. However, the responses have been slov. A more effective means of refining the schedule has been the "SYSTEM OF THE DAY" meetings. These meetings take two to three specific systems, analyze each activity and adjuet schedule duration, logic or required resources. Every group who has any responsibility for activities in the revieved systems are urged to attend and respond. The generic activities in the schedule are also being replaced by maintenance work orders. All PMV0's have been inputted into the schedule, while 759 corrective and 210 modification MV0s have been input to the schedule. t 1 l l 1 l 1 I A R TURBINE AND TURBINE GENERATOR ACTIVITIES
~~ - ~ -
~ - - - - - - - - - - - - - - - - - - - - --
TURBINE AND TURBINE GENERATOR ACTIVITIES SCOPE:
- 1. MAIN TURBINE A. H P TURBINE REPLACE FIRST STAGE BUCKETS (2 ROVS) TO ALLOV PARTIAL ARC ADMISSION OPERATIONS.
BORES 0NIC CLEAN AND INSPECT FRONT STANDARD BLAST CLEAN ROTOR AND DIAPERAMS NOTE: THE RESULTS OF THE TORSIONAL TEST VILL DETERMINE VHICH, IF ANY, L P TURBINE VILL BE ' DISASSEMBLED. DEPENDING ON THE RESULTS EITHER L P "A", or L P "B", OR L P "A" AND "B", OR NEITHER VILL REQUIRE DISASSEMBLY AND a TIE-VIRE INSTALLATIONS. B. L P "A" INSPECTION TIE VIRE INSTALLATION DIAPHRAM REPAIR VHEEL SONICS BLAST CLEAN ROTOR AND DIAPHRAMS C. L P "B" INSPECTION TIE-VIRE INSTALLATION VHEEL SONICS t
- BLAST CLEAN ROTOR AND DIAPHRANS *
, D. BEARING INSPECTION INSPECTION VILL BE PERFORMED BASED ON VORK SCOPE DISASSEMBLY
- i HP TURBINE - BEARING I AND 2 L P "A" TURBINE - BEARINGS 3 AND 4 ;
L P "B" TURBINE - BEARINGS 5 AND 6 ' GENERATOR - BEARINGS 7 AND 8 ' ALTERREX - BEARINGS 9 AND 10 1
- 2. GENERATOR /ALTERREX i
A. SHIP FIELD TO GENERAL ELECTRIC SHOP IN CHICAGO j B. PERFORM COPPER DUSTING REVIND OF FIELD (CHICAGO) C. REPLACE FIELD RETAINING RING VITH IMPROVED MATERIAL (CHICAGO) D. i REPLACE GENERATOR MAIN LEADS (CHICAGO) E. CLEAN, INSPECT, AND VARh SH GENERATOR STATOR T. CLEAN AND INSPECT ALTERREX G. REPAIR ALTERREX COLLECTOR RINGS
- 3. ELECTRO HYDRAULIC CONTROL A. REBUILDING ONE EHC PUMP B. NORMAL P.M.'S
- 4. TURBINE VALVES A. INSPECT TVO MAIN STOP VALVES B. INSPECT TWO CONTROL VALVES C. INSPECT TVO COMBINED INTE;tMEDIATE VALVES D. INSPECT TWO REHEAT SAFETY VALVES CHECK SET POINT ON ALL VALVES DURING START UP
- 5. MOISTURE SEPARATOR REHEATER A. OPEN AND INSPECT FIRST AND SECOND STAGE TUBE BUNDLE AREA B. PARTIAL IMPLEMENTATION OF FCR 81-223 VHICH CHANGES MANVAYS TO AN EXTERNAL BOLT ON DESIGN SIX OF TEN MANVAYS ARE BEING PROPOSED FOR EACH MSR BY DESIGN ENGINEERING. TME ,
SIX SELECTED VILL SUPPORT THE AB0VE INSPECTIONS.
- 6. IMPLEMENTATION OF PRIORITY TIL'S AND ECN'S
- 7. MAIN FEED PUMP TURBINES A. MAIN FEED PUMP TURBINE NUMBER I AND NUMBER 2
- l DISASSEMBLE, INSPECT AND REASSEMBLE 8.
MAIN FEED PUMP TURBINE NUMBER 1 AND 2 HIGH PRESSURE AND LOV PRESSURE STOP VALVES DISASSEMBLE. INSPECT, LAP AS REQUIRED l AND REASSEMBLE l 1 l 1
l
. . t f
STATUS: Vork Scope's of the "A" and "B" L P turbines is contingent on the torsional test results. Partial ARC modification vill be performed on the HP turbine but no vork vill be done on the nozzle block. The generator vork vill be performed at General Electric. Both main , feed pump turbines vill be vorked during the outage and half the main steam valves vill be inspected. General Electric vill be responsible for the score of this work. The MSR proposed work scope is to work six of ten j aanvays per MSR. The durations and start dates vill be determined after the improved manvay design, which was approved by design engineering, is received from General Electric. The Purchase Order (Number 00802350), which covers material procurement only, has been issued. Task authorizations have been issued to General Electric to initiate long lead material procurement. Purchase Order 00802350 also covers the work scope in , proposals 390R87031906A and 230747025. Tasks have been l issued for the General Electric for long lead material procurement and work procedure preparation. A Purchase l Order 01248550 has been issued for General Electric site engineering services. Preliminary General Electric work schedules were received this month for Toledo Edison review.
- i One QA and approximately twelve maintenance procedures l are under development to address QA's concerns that !
General Electric perform quality work. j CONCERNS:
- 1. Turbine / generator vork vill share the critical path for the 5th Refueling Outage as it is estimated to take 13 veeks.
- 2. Final vork schedule from General Electric to coordinate with Davis-Besse's Vork Planning Schedule (P-2). j j !
~
- 3. Establishing and coordinating approved vork area for contaminated turbine, and MFPT components.
1
- 4. Rail repairs are underway to ensure the Toledo Edison right-of-ways are at the maintenance level required for transport of the main generator off-site to General Electric and returned to Davis-Besse.
]
e a FUEL EANDLING ACTIVITIES l l 1
FUEL HANDLING ACTIVITIES SCOPE: The scope of work scheduled for the Fifth Refueling Outage includes defueling, refueling and the UT of the upper core barrel bolts. STATUS: New fuel delivery dates are planned by Performance and Nuclear Engineering as January 6 through January 30, 1988. This vill include 8 "Gray
- APSRAs and 64 BPRAs.
The fuel loading & shuffle scheme vill be based upon the B&V reload report received this fall. PP1504.02 (Fuel / Control Component Shuffle) vill be revised to reflect the B&V reload report. The Reload Report and License Amendment Request (FCR 84-067) is expected to be submitted to the NRC on February 15, 1988. The Reload Report and License Amendment Request was approved by the SRB in late November,1987 and is expected to be submitted to the CNRB on December 10 1987. The expected date for the License Amendment (restart July 15, Mode 1988 2based approval) from the NRC is approximately on a February 15. 1988 submittal. FCR 83-007 vill modify fuel grapples and control rod mast on the Main Fuel Handling Bridge. This CTMT modification vill take two weeks to implement. This work is to be performed prior to performing PT 5181.01 (Fuel Handling Equipment Periodic Test). Current plans are to implement FCR 83-007 on the Fuel Storage Bridge when divers are available November 30 through December 4, 1987. Preliminary work required for new fuel receipt is scheduled and/or underway. This work includes the Spent Fuel Pool Cask Crane, New Radvaste Building door cut-out, the procurement of New Fuel Handling slings, the fabrication of temporary control components storage and the clean up of the train bay area. The spent Fuel Pool Cooling Outage Preliminary work is complete. The decision has been reaffirmed to UT the Upper Core Barrel Bolts in the Fifth Refueling Outage with replacement as a contingency only in accordance vith the Project Plan. CONCERNS: The RV plenum assembly when removed for refueling is staged in the deep end of the refueling canal. Currently, there is material from the RCP shaft changeout in this area. l
l INSERVICE 1 INSPECTION ) l ACTIVITIES i ,1 I, 4 1 i l 1 4 I l 1 I s 19 4
ISI ACTIVITIES SCOPE: Approximately 500 ISI (Inservice Inspection) Activities are planned for the 5th Refueling Outage. The activities by area are as follows:
- a. Containment
- 1. Eddy Current testing of tubes in both OTSG's.
- 2. Ultrasonic testing of shell and nozzle velds in both 01SG's and the pressuriser, the flange /shell veld in the RPV (Reactor Pressure Vessel) and various piping velds.
- 3. PT/MT of various piping velds.
4. MT/VI of RPV head bolting.
- 5. Pressure testing of the RCS and other systems.
- 6. Visual inspection of various component supports and valve internals.
- 7. UT core barrel bolts.
i
- b. Auxiliary Building
- 1. MT/PT of various piping and support velds.
- 2. Visual inspection of various component supports and component bolting.
- 3. Pressure testing of various systems.
- c. B.O.P. (Balance of Plant)
- 1. Erosion Corrosion UT inspections.
- 2. Eddy Curreat testing of condenser tubes and feedvater heaters.
STATUS: Detailed P/2 information has been developed and inputting is underway. Budgetary quotations have been received from B & V for the 0TSG Eddy Current with final task description and detailed cost data was provided at the end of September. Performance Engineering has reduced the number of Feedvater Heater Eddy Current exams from eight to two. (H P heaters E4-1 and E4-2). Core barrel bolt inspection has been established at Upper Core Barrel bolting only.
Request for bids for Main Condenser and Feedvater Heater Eddy Current Testing was sent out Mid-November reply expected Mid-December. A meeting to discuss ISI craf t support and work order requirements was held before the end of October. System Engineering has generated their reconsendations regarding the extent of OTSG Eddy Current exams and bubble testing. These reconnendations are being forwarded to the Plant Manager. CONCERNS: Feed Vater Heater and Main Condenser MVOS needed for
~
scheduling. in progress FCR 87-119 (Tech. Spec. change for Eddy Current Inspection) must be issued prior to refueling to implement the tube inspection scheme proposed by Engineering. COST Total ISI cost is estimated at about $1,000,000 at this time, plus craft support which could be as much as
$500,000 in labor.
1 D E l I l 1 INTERATED LEAK RATE TEST ACTIVITIES
. . i i
i l ILRT ACTIVITIES l q SCOPE: The scope of this activity is to perform DB-PF-03400.4 l
.i STATUS: Performance Engineering vill revise the ILRT test i
I procedure (DB-PF-03400.4) upon receipt of information from Design ingineering (RFA 87-778). This RFA vas , expected to be supplied by September 30, 1987. l l Performance Engineering is currently reviewing the CTNT changes which vill be used in the procedure revision. A reply to the RFA vill be received by November 30, 1987. ; Devpoint and flow meter instrumentation is nov scheduled to be shipped of f-site for calibration in late December and is scheduled to be returned just prior to the ILRT j start date, which has been scheduled just after . i re-fueling the reactor Mid-July, 1988. l i ( a h 1 1 l I L I l
-23 l
I I l i l l I i I 1 1 1 MODIFICATION ACTIVITIES i i l 1 i I 4 4
\
l 24 1
1 MODIFICATION ACTIVITIES i E SCOPE: The scope is identified as all 5R Licensing Required and SR Improvement Modifications in the work scope for the Fifth Refueling Outage or 05 Modifications requiring completion prior to the end of 5R. STATUS: There are currently 134 ;5R) modifications (FCR/ MOD) scheduled for laplementation during the Fif th Refueling Outage. The total nursber of modifications is frozen, however the number of supplements to each modification is fL?t w ins as design packages are nearing completion. 1 Engineering is projecting the delivery of approximately 70 ' detail design packagts for final processing during the month of December. Major effort vill be required to , i process this number of packages by the start of 1968. Additionally, this should release a significant amount or pre-outage work in a very short period of time. One issue of conceirn is the slippage of Control Room Human Engineering De!!ciency (HED) modifications detail design completion dates into the Fid-December time frame. A
!gnificant this amount of pre. outage work vill be impacted by slippage. Operations. Outage Management and ,
Facilities Modification Department are working c.osely to accomplish the available pre-outage work in the cable , spread room. ! Modification material is still a major concers. in general. Special attention is being afforded long lead Material i that is still maintaining delivery dates in the outage time frame. The continuing release of detail design i engineering packages are generating material orders daily. 1 Close attention must be paid to ordering and delivery of l material to support scheduled implementation. Plant modification vork orders currently number about 200. It is projected that approxicately 800 MV0'S vill be required in support of 05R modification implementation. 1 OPEN MOOS /SilPPS MODIFICATION STATilS CYCL.E 5R CONCEPTUAL DETAll.ED ENGINEERING NON-0UTAGE OITTAGE CLOSE0lfT ENGINEERING H ATER I A'r 8/11 93* 31 134 137 Not Started 4/4 4 0 0 In Pcogress 3/3 81/98 - 49 38** 4 2 0 Completed 103 7 N/A 100 3 2 Not Applicable 29 1 139 N/A 139 139 139 TOTAL 139 4
- Represents material not here i
** Represenats material here i
j i
8 - DATA DATE 1 85/29 8I SAS RUN DATE I 11/23/87 MODIFICATION STATUS CYCLE SR ACTIVITY DESCRIPTION COMIT A/E CDP DDP MTL N/O OUT C/O ENG SCM TYPE COMP 77-0394 CHANGE MSIV SYPASS VALVES TED E I E E , , 2/27/07 79-0229 INSTALL FLANGES IN LINE HSC-117 TED E I , N/A , _ 2/27/07 00-0027 INSTALL CTMT CAGE D-RING 40-02 TED E E I N/A , _ 2/OS/s?
$1-0062 MODIFY O/G LUBE OIL SYS TED E E ,
N/A , , 2/27/87 08-0223 MSR SOLTS ON MANWY PRG REV A TED A A _ N/A , _ 3/13/03 83-0007 REPLACE F/M CORTROL ROD MASTS TED E I E A _ _ 2/27/47 e3-0076 REPLACE UPPER CORE SABREL SOLTS TED I I E N/A , , 2/27/87 83-053e REPLACE SW-24 TED E I E N/A , , 2/27/87 3 43-0139 NEW JAMESEURY VLVS FOR SW SYS TED E E , N/A , , 9/08/87 I 83-0151 REPLACE FISMER BF VALVES NPC(F) TED E E , N/A , , 10/26/07 83-ul64 REPLACE SAILEY RECORDERS BPC I I , , , , 10/16/07 34-0002 ADD STIFENERS TO CRDM PLATFORM NRCtF) B/W I A , , , , 32/20/87 84-0018 REPLACC RCS VALVES NRCEI) TED E A I N/A , , 1/28/88 84-0049 SAFETY GRD INCORE DETECTORS NRCdID SPC E A , , , , 12/14/07 84-0067 REFUEL REACTOR TED E A I N/A as/A , 7/11/80 84-0068 MOVE MSR DRN CONTRO. V LVit MACIF) TED N/A A , A- , , 1/06/88 84-0003 REPLACE STATION MULTIPLEMER NRC(I) TED E I I A , , 7/31/07 84-0501 RV HEAD LIFT DEVICE 9/W X X A N/A , , 10/05/07 e4-0504 MODIFY N2 SYSTEM ELECT PENET TED E I I N/A , , 2/27/07 e4-0183 VELAN CHECE WALVE MODS NRCdF) TED E I A N/A , , 9/50/07 04-0816 NEUTRON FLUE EQUIPMENT NBC(Il SPC E A , , , , 12/84/87 e4-08SO rn POLAR CRANE SAFETY CASLE TED N/A N/A N/A N/A , , 3/82/87 I = COMPLETED A = IN PROGRESS , = NOT STARTED N/A = NOT APPLICABLE BPC = SECNTEL POWER CORP, CYG e C7GNA S&W = BASCOCE & WILCOM
$6W = STONE 6 WESSTER 86R = 3ROWM & ROOT
ee I . DATA DATE 11/23/87 SAS RUN DATE 11/23/87 MODIPICATION STATUS CTCLE SR ,
--...-..---..--.----------------------------------......-~~~-------------------....--..--...._- _--- .---. . --..-. .--_
ACTIVITY DESCRIPTION COMIT A/C CDP DDP MTL N/O OUT C/O ENG SCM TYPE COMP
- - - - - - - - - - - - - - - - - - - - - - - - - . . - - - . - - - - - - - - - - - - - - - - - . . . - - - - - - - - - . - - - - - - - - - - . - - - - - - ~ ~ - . . - - . . . . - - - - - - - - - - _ ----.-------
04-0177 INSTALL ISO AC100,109.AD408.109 NRCtI) TED I A N/A 12/16/87 84-0190 ALIGN AF-)S72 OPEN NRC8F) TED I A I N/A I/27/88 85-0024 INSTALL TEMP REACT CAV DOSIMETRY TED E A A N/A 12/I4/87 85-006S Arw IMPROVEMENTS AND LEAE TEST NRC(FI TED N/A A E N/A 11/24/87 85-0096 ADD REDUNDANT SG LVL/ PRESS IND NRC(F) SPC I A , , N/A S/10/07 8S-0409 INSTALL NEW CAS IN CTL RM NRC(F) RPC E A , , S/28/87 85-014) SS O-RING SOR PRESS VALVE TED N/A I A N/A N/A 8/24/87 85-0154 DEL SFRCS OPN/CLO SIG TO APIV NRC(FI TED I A N/A N/A 11/24/07 i y 8 85-0157 LOwrp $rRCS low LvL TRIP SP NRCtrl TED x x x N/.A 10/05/87 03 I SS-0207 DEPLACE CROM VENTILATION FANS NRC(!) RPC I A , , 32/23/87 85-0245 AFPT GOV VLV SEAT DRAIN BPC I I , N/A 9/23/87 85-0264 RESERVE RESOURCE SELECTOR SW NRClIl TED I I E N/A 2/27/87 85-027) ARTS Ex PwR SISTABLE LAMP CRT NRCell TED I I N/A 2/27/87 SS-033) MAIN STEAM VISRATION MONITOR NRC(F) TED E E I N/A , , 1/02/87 84-0021 ADD ARTS ALARMS NRCt!) OPC I A N/A 2/08/08 46-0010 REPAIR FIPC SUPPORT 40-CCS-16-M) NRC(FB TED E I N/A I E _ 2/27/07 86-0038 ADD LIMIT SWITCN/LIMITORQUE NRC(Il SPC E A N/A 12/07/87 86-0036 INSTALL RCS PI IN CONTROL RM NRC(Il TED X A 1/07/88 46-0038 ADD PRESS GAUGE NEAR NN-409 TED E E N/A 2/27/07 86-006) MLPAIR DEGASIFIED WATER PMPS TED E I I N/A 1/02/87 86-012) REACTOR Pwn AUCTIONEER TO ICS NRCil) TED E A N/A 12/07/87 86-0137 Rcr GA* RET DRAIN TED E I I N/A 2/27/07 I = COMPLETED A = IN PROGRESS , = NOT STARTED N/A = NOT APPLICABLE SPC = BECMTEL POWER CORP. CYG = CYGNA Saw = BABCOCK & w!LCOE
$6w = STONE & WESSTER SER e BROWN & ROOT
3 SAS RUN DATE 4 11/23/87 DATA DATE 11/23/SI MODIFICATION STATUS CYCLE SR DDP MTL N/O OUT C/O ENG SCM COMIT A/E CDP ACTIVITY DESCRIPTIO4 COMP TYPE TED I I , , _ _ 2/27/87 86-0157 CONTROL ROOM REMEAT C01LS TED I I N/A , _ 2/27/87 INSTALL ANTI-ROTATION FINS 86-0160 TED I I I N/A , , 2/27/07 86-0175 REPLACE VALCOR SV SPRINGS MRCtF) SPC I A , , , , 12/07/87 86-0192 REPOWER SU FEEDWATER PUMP TED I I , N/A , , 9/17/87 86-0200 ANTI-ROTATION PINS FOR MS$V"5 NRClFI SPC N/A A , , A/A , 12/14/87 86-0201 INST MSSV & AVV POS MONIT TED N/A I , W/A , ,
$/13/87 46-0251 REPLACE CCW STOP CNCCE VALVES TED I I A N/A , ,
11/10/87 86-026) REPLACE PSA MECMANICAL SNUBSER NRCll) TED I I A N/A , _ 2/27/87 h$ 86-0291 MODIFY NPI/MU SYS FLOW TST LN I WRC(F) 8FC I A , , , 12/07/87 96-0318 RELOC NOT LEG MONITOR STS-TUBING , TED I A A , , 1/04/88 REPL IFERS CONTAINING PCB , 46-0328 BPC I A 12/09/87 IMPROVE STAS-AUI FEED SYSTEM NRCIII , , , , 86-0130 TED I A I afts/88 PC%Q , _ , 86-0346 COOL TOWER mEAM s SUPPY MODS TED N/A I N/A N/A , , 11/06/06 86-0972 REMOVE LFC CRT FROM ICS TED I I I N/A , , 6/12/87 86-0176 REPAIR SUPPORT 20-MSD-06-N17 TED I I , I , , 1/13/87 86-0197 REPLACE RECTIFIER FLOWMETER TED I I I N/A I , 3/16/87 86-0401 PI-SC2A6 INSTR CRT DESIGN TED I I N/A , , S/04/07 INSTL CF-30 6 31 ANTI-RTN DVC 86-040) NRCdFf BPC I A , A , _ 12/21/87 86-0425 RELOCATE MDFF CONTROLS TED I A 12/11/87 NRCIF) _ , , , 86-0432 M /if FEED 6SLEED-QUAL EQUIP TED I I I I , , 4/20/87 87-0012 REPLACE COND FOL SEPTUM TUBES I W/A 3/20/07 TED I , 87-0021 REVISE LIMITORQUE LMT SW NUMBR$ I = COMPLETED A = IN PROGRESS ,
- NOT STAATCO N/A
- NOT APPLICASLE BPC = SECMTEL POWER CORP. CYG = CYGNA S&W = SABCOCK & WILCOM S&W = STONE 6 WEBSTER R6R = BROWN & ROOT
a e
- DATA DATL I 18/25/e7 SAS RUN DATE : 11/23/87 MODIFICATION STATUS CYCLE SR DESCRIPTION COMIT A/E CDP DDP MTL N/O OUT C/O ENG SCH ACTIVITY TYPE COMP e7-002) INSTALL MFPT THERMOCOUPLES TED N/A I E N/A , ,
13/02/e7 87-0037 REPLACE PG 4) NRC(F) TED N/A I N/A N/A , , 6/12/87 87-0054 $US OF STRUT POR A SNUSSER MRC(F) TED E I E N/A _ _ S/05/87 87-0063 RELOCATE SFAS SIGNALS NRC(F) BPC W/A A I , N/A _ R2/21/07 07-0064 RELOCATE AFw CONTROLS NRC(Fl SPC E A I , , , S/le/87 07-0065 SFRCS BLOCK SWITCNES MRCtFB SPC E A E N/A _ _ 12/18/87 87-0066 CNTRL RM CONSOLE C-5706 . L-5710 NBC(P) BPC E A E , _ _ 11/10/87 37-0067 NEW CONTROL ROOM CONSOLE NBCEF) SPC E A E , , , 12/07/87 8 07-0064 AFPT DISCMG PRESS /SPEE? IND NRC4F1 SPC E E 10/06/e7 87-0069 REPL AFW FLOW INDICATIONS NRCIF) SPC N/A A A _ _ , 12/10/07 87-0070 CONTROL RM CONSOLE C-5721 NBC(F1 BPC I A E N/A , , 12/10/87 87-0071 CNTRL RM PMLS CS701.5724,5798 NRC(F) TED E A A , , , I/06/88 87-007) CONTROL ROOM CONSOLE C-S717 NRC(F) SPC E A I , _ _ 32/29/s7 87-0080 RELOCATE TEMP ELEMENTS TERC12 26) NRClI) TED N/A A _ N/A _ _ 12/04/87 47-0009 REPLACE FORV PPG & SUPPORTS TED N/A I N/A N/A , , S/08/07 87-0092 MDFY SFRCS/SFW MAN. INI. SWIT ORCIFl SPC M/A A , , , , 12/19/07 87-0104 MOD FSK-M-NSC-162-2-Al BPC I I _ N/A , _ 6/12/07 87-2010 PRES $URIEER NEATER ADAPTERS TED N/A A , N/A _ _ 1/07/88 07-8011 INST FLOW METERS OMAFWP RECI TED , _ , N/A , , 12/IS/87 07-1089 ADD SFAS RAD MONITOR CNNCTR PCAQ TED N/A A I N/A , _ R2/23/e7 e7-102 REPLACE *SOR* SWITCNES TED E A , N/A , , S/tt/88 07-4025 rNANGE SCREWS T3-4 IN ARTS CAB TED _ , , N/A _ , 11/50/47 I - COMPLETED A = IN PROGRESS , e NOT STARTED N/A = NOT APPLICABLE SPC = BECNTEL POWER CORP. CYG = CTGNA B&W = OABCOCR & WILCOE s.. . <,n r . wr.<,r. ... . Rn-N . RonT
S . SAS RUN DATg 11/23/87 DATA DATE 11/23/87 MODIFICATION STATUS CYCLE SR COMIT A/E CDP DDP MTL N/O OUT C/O ENG SCN ACTIVITY DESCRIPTION TYPE COMP
.----------.---------- ---.-------.--.--------------------------------------.----.-~~---------- =
INSTL ROD STOP CIRC. TED N/A A N/A 1/04/88 87-30)1 , _ , REPLACE MOT-20 POSITION S SOARD TED N/A A N/A 1/07/88 87-1933 , , , TED I A I 12/07/87 87-103S REDES SG NTO $NUSA LOAD FINS , _ , MRCit) SPC I A A 12/17/87 87-1062 UPGRADE STA/ INST AIR NON-OUT , , , TED I A N/A N/A 3/03/88 87-1011 SERVICE WATER CNECE VLVS _ _ SERVICE WATER CNECE VALVES TED I A N/A 1/29/88 87-1072 , , , 87-1073 REPL SW-329 W/CNE VLV TED I A , N/A , , 1/15/88 BEM INTERNAL FROM AF-11612 TED N/A N/A 1/21/88 87-1014 , , _ _ 2 0 CTRL RM EVS SW 1306124 TED N/A A W/A 2/16/88 y3 87-1475 , , ,
. TED N/A A N/A 2/19/88 87-1976 REM INTERNALS FROM SW217&218 , , ,
87-1081 REPLACE BATCM CNTRL IN MU6F SES NBCtt) TED I I I N/A , , 10/09/87 87-1085 r s. s . CNTRL RM ANNUNCIATR FST OUT FEA NRCtrl TED N/A A I N/A _ , 12/18/87 NRCit) TED A A W/A 1/19/08 87-1992 ACS/MMI AUTO-SELECT SWITCM , _ , 87-1093 MRS DIRECTN ERROR MOD & CET NBCGI) TED I A I N/A , _ 12/31/87 REPLACE OBSOLETE SAILY INSTR TED I A W/A 1/21/88 87-1800 , , , REMOVE STU LIMITS FROM ICS TED I I N/A 9/17/87 87-1101 _ _ , 87-1102 PROVIDE SFAS SNUTDOWN STPASS MRCIII TED I A I N/A , , 12/11/87 REMOVE ICS AFW CET TED I I N/A 9/22/87 87-1104 _ , , NRCil) TED N I N/A 10/01/87 87-1105 REMOVE ICS AFW CET , , , 22C(!) TED I A A N/A 12/21/87
~ F; ?,807 IMPROVEMENTS TO SFRCS PER DNRTF , ,
rROVIDE REFLASN CAPABILITY 10-2-1 & NRCIF) SPC I A A N/A 2/08/08 87-1108 , , rRoVIDE REFLASN CAPABILITY 1-4-1 NRCtF) SPC I A N/A 1/34/88 87-1110 , , _ I = COMPLETED A = IN PROGRESS , a NOT STARTED N/A
- NOT APPLICASLE SPC = SECNTEL POWER CORP, CTG = CYGNA 86W = SASCOCE & WILCOI S&W = STONE 4 WEBSTER B&R e SROWN & BOOT
SAS RUN DATE : 11/23/07 DATA DATE 11/23/47 NODIFICATION STATUS CYCLE SB COMIT A/C CDP DDP NTL N/O OUT C/O ENG SCN ACTIV1TV DESCRIPTION COMP TYPE NRC(F) SPC I A N/A 1/22/88 87-1111 PROVIDE REFLASM CAPABILITY 116 , _ _ NBC(F) EPC I A N/A 1/22/88 87 1112 PROVIDE REFLASM CAPASILITT 1-1-5 , , , 4 NBC(FD erc I A N/A 1/22/83 87-1113 PROVIDE REFLASM CAPASILITY 1 1-4 , , , PROVIDE REFLASN CAPASILITV 1_1_) NRC(F) SPC I A N/A , , 1/22/88 87-1314 , NRC(F) SPC I A N/A 2/01/08 87 1335 PROVIDE REFLASN CAPASILITY 14-1_4 , _ _ NRC(Fl EPC I A N/A 2/01/88 87-1116 PROVIDE REFLASM CAPASILITT 14 1-S , , , PROVIDE REFLASM CAPABILITY 16_3-6 NRC(F) SPC I A N/A 1/14/08 87 1117 , , , PROVIDE REFLASM CAPASILITY 1-4_2 NRC(F) SPC I A N/A _ 1/14/S$ 87 1118 , _ PROVIDE REFLASM CAPASILITT 1 4_3 NRC(F) SPC I A N/A 1/14/88 07_1119 , , ,
- d. NRC(I) S/W X A A N/A 12/21/87 87-1124 INSTALL NOSING CCW STATOR LINE , ,
NRC(F) TED I A 12/28/87 87-1130 REPLACE PAN PANELS , , _ , UPGRADE STATION / INST AIR NRC(I) SPC I A _ _ R2/10/07 87 1130 _ _ TED I A I N/A 1/05/08 07-1141 CIRCUIT SREARER FAIL PROT TRIP , _ GENERATOR TRIP FOR STATOS GROUND FAU TED I A A N/A , 12/28/07 87 1142 , NRC(Il TED I A A N/A 12/21/87 87 1147 NPI FLOW INDICATORS , , ADD SNUBBERS TO NS$V ENC LINE TED N/A A N/A , 1/19/88 a 57 115$ , , NRC(I) TED I N/A 1/20/88 47_1160 NODIPT LIMITORQUE CONTROL SCNENE , , , , NODIFJ COOLED COND PPG CONN TED N/A I , 30/03/47 87 1161 , , , TuRSIME GENERATOR WORE TED N/A A , 12/28/87 87-8164 _ , , TED N/A A N/A N/A 1/12/80 87-1866 TOTAL FLOW CONTROLLER REMOVAL , , NRCEI) S&W I A A N/A 1/27/80
$7-1168 BEPLACE DECAT NEAT REMOVAL VALVES , _
NRC(81 TED N/A I N/A 1/2%/88 87 8174 ICS SIGNAL LIMITER $ , I e COMPLETED A = IN PROGRESS , a NOT STARTED N/A e NOT APPLICASLE SPC = SECNTEL POWER CORP. CYG e CYGNA S&W = SABCOCE & WILCOI
$6W = STONE & WE85TER SLR = SBOWN & ROOT
7 r DATA DATE 4 11/23/87 SAS BUN DATE a 13/23/87 MODIFICATION STATUS CYCLE 59 ACTIVITE DESCRIPTION COMIT A/C CDP DDP MTL N/O OUT C/O ENG SCH TYPE COMP 87 3382 DM 2733 & 2734 GUIDE MODIFICATION TED N/A A A N/A , , 1/13/80 87-139) REPL TNE EXISTING PASS SYSTEM TED I A , N/A , , 2/29/80 87 389$ ECCS DOOMS SUNP PUMP PIPING TED A _ _ N/A , , 2/03/88 87 3898 NEPL. AP599 & 408 W/ 900 0 CL 2 VLWS NaCIP3 TED , , , N/A , , 2/0$/88 47 1258 SECOND STARTER FOR DN098 & DN09A NRCIII TED E A _ N/A , _ 12/10/87 07-827) AUM PEEDWATER PUMP TUpeINES TED N/A A , N/A , , 2/10/80 87-1296 ENHANCE M.S. PRESS. RELIEF INSTRUM. TED - - - N/A - 3/07/88 8 1 W < w I i i I = COMPLETED A e IN PROGRESS ,
= NOT STARTED N/A = NOT APPLICABLE t
t j SPC e SECNTEL POWER CORP. CYG = CTGNA AsW
- SABCOCK & WILCOE Saw = STONE & WEBSTEa san . spOWN s ROOT
= . l
- s l
l l l CORRECTIVE AND PREVENTIVE MAI!frENANCE ACTIVITIES 1 l i I 1 l CORRECTIVE AND PREVENTIVE MAINTENANCE SCOPE: Presently approximately 1764 MV0's are outage related of which 759 are Corrective and 765 are Preventive Maintenance. These are being revieved for validity and proper scheduling. STATUS: A Breakdown of the current MV0's that are classified as Outage Corrective MV0's and Outage Preventive MV0's indicates the following status: OUTAGE CORRECTIVE MV0'S In Planning - 383 Ready for Issue - 376 Total 759 OUTAGE PREVENTIVE MV0'S In Planning - 760 Ready for Issue -- 5 Total 765 The remaining 240 MV0's are: J l
'* 210 MVO generated to support MOD's 30 MVO generated to answer PCAQ's I
)
1 l l l l l 1 1 l MANPOVER PROJECTIONS
MANPOVER PROJECTIONS The following attachment is a compilation of all the manpover requirements identified to date by type and work effort. Outstanding concerns are:
- 1. A significant amount of ST's have not been added into the breakdown but are expected to be input in the schedule by January 1, 1988.
- 2. Only 120 of the 134 MODS identified have had resource requirements entered into the Outage Schedule. The remainder are projected to be input by January 1, 1988.
- 3. Although approximately 25% of the scheduled work can be vorked as pre-outage work, delay to Engineering vork package issuance and untimely material delivery have the potential to cause this vork to be implemented during the outage vindow.
4. A significant number of 05 FCRS vere experiencing Implementation impairments which vould caure an overflov of non-outage work into the pre-outage work. Outage Management submitted a differentiation report detailing priority for 05 and 05R to the Davis-Besse Vork Scope Committee and recommending 05 vork to be rescheduled until after the Refueling Outage. Twenty-eight 05 FCR's (implementation portion only) were deferred or voided by the DBVSC i on October 23, 1987 vhich should resolve this i concern.
- 5. Final reviev of each vork activity for accurate Manpover Projections still remains to be accomplished by most station departments. This is projected to be complete by January 15, 1988.
It should be noted that the needed manpover estimate was reduced when the outage duration was extended from three to six months. However, manloading vill not reduce critical path duration. F ~ FIFTH REFUELING OUTAGE MANPOVER ESTIMATE
/f
/h /
/f/f v /& /
/ /
/ h. /
/ h/ /
/ / &*/ / \ / /
/y TED
......... /
/ f/$*/
/
/ N' / kh / N /g
/ / / / /
MECH 13.5 10.8 11.5 1.8 0.1 0.0 ELEC 2.9 5.8 5.5 0.1 0.1 0.0 I&C 2.1 17.3 3.1 3.7 1.0 0.0 SERV 5.4 2.3 1.4 0.1 0.1 0.0 SUBTOTAL 23.9 36.2 21.5 5.7 1.3 0.0 88.6 CONTPACT MECH 25.2* 8.4 0.0 0.00 0.3 ELEC 59.1 0.0 0.0 0.0 0.0 OTHER 14.7 39.0 21.0** 0.2 2.4 65.1* SUBTOTAL 14.7 123.3 29.4 0.2 2.4 65.4 235.4 l SUPPORT HP/ RAD COD 3.0 61.8 0.6 0.6 1.9 0.0 t QC 2.5 10.0 1.2 1.4 0.2 0.0 SUBTOTAL 5.5 71.8 1.8 2.0 2.1 0.0 83.2 TOTALS
..d......
TED CONTRACT 35.6 SUPPORT 2 35 t.
............................................................,....63.0 ..
TOTAL 407.2 ; i l Per G.E.'s Estimate
** Includes Contingency
~
l. l l WORK IDENTIFICATION TARGET LINE - 700 I 812.9 l see _ START OF REFUELING j 500 e
- 41s.s MEU ON SITE 400 _
g 3,g,g M .2
;$ s.. _
27s.s i 200 _ ! 143.5 i isc _ 1 1 i 0
- I I I I I I I I I I I
)
MAY JUN JUL AUG SEP OCT NOV DEC JAM FEB MAR APR e PRESENT EST MANPOWER e OUTAGE MANPOWER NEED PROJECTION q (BASED ON EXPERENCE) l L___ _ _ - _ _ - . - _ _ - _ _ _ _ _ - - - - - - _ _ _ - - - _ - _ _ _ ____ __ _ _ _ _ _ _ _ _ _ _ _ - - - - _ _ _ _ _ _ _ _ _ _ _ ____ __--.___ _ _ - -_
1 1 { l 1 1 l i f ( l c i FINANCIAL I l i i t 1 l l 1
i I FINANCIAL SCOPE: The intent of this section is to present a breakdovn of the current 05R budget under a major heading concept. Contracts and Budget department has collated cost data for the 1988 budget, a major portion of that budget contains the Fifth Refueling Outage Costs. The available modification cost data appears in a condensed format with 1987 and 1988 estimated cost provided. A review of the SR modifications 1987 cost to date l compared with 1987 estimated costs reaffirmt, that several I modifications require an accelerated procurement and l implementation effort in order to properly support the i planned installation schedule. l l i i I 1 4
FIFTH REFUELING MODIFICATION COST BREAKDOVN The following modification cost breakdowns (costs spent in 1987) were computed as of November 22, 1987. It should also be noted that estimated costs for seven modifications were not identified for this publication. 05R LICENSING REQUIRED MODIFICATIONS: 1988 1987 ESTIMATED ESTIKATED 1987 COST THROUGH NO. OF MODS COST COST 11/22/87 O&M 14 $ 467,900 $ 452,000 $ 306,661 Capital 59 S10,038,600 $5,917,800 $3,975,857 OSR IMPROVEMENT MODIFICATIONS: I 1988 1987 ESTIMATED ESTIMATED 1987 COST THROUGH l NO. OF MODS COST 11/22/87 _ COST ] 0&M 44 $8,115,600 S 724,900 $ 132,585 1 l Capital 22 $8,402,400 $1,498,700 $ 667,557 05R MODIFICATIONS TOTAL: 1988 1987 , ESTIMATED ESTIMATED 1987 COST THROUGH l COST __ COST 11/22/87
$27,024,500 $8,593,400 S5,082 660 l
1
l 05R LICENSING REQUIRED MODIFICATIONS ESTIMATED ESTIMATED COST COSTS COST THRU CHARGE MOD DESCRIPTION _ 1988 1987 11/22/07 ACCOUNT 83-139 New Jamesbury Vlvs for GV Svs 2,100 24,000 19,109 6433-1 83-151 Replace Fisher BF Valves 3,000 50,000 45,964 6233-1 84-002 RV Head to Hot Leg Vent 243,000 663,000 263,368 6215-1 84-018 Repl RCS Valves 5,000 10,500 0 5014-1 84-049 Inst Safety Grade Incore Dtr 1,036,500 208,300 185,723 6267-1 84-068 MSR Belly Drn Hi-Loc 50,000 90,000 78,351 3978-1 84-083 Rep 1 Station Multiplexer 430,000 350,000 333,695 6291-1 84-113 Velan Check Viv Mods 8,500 8,800 0 6334-1 84-116 (Sup 0) Neutron Flux Equipment 566,000 190,000 170,560 6278-1 84-177 I n !. ' Iso AC108,109, AD108,109 13,000 6,500 0 6388-1 84-190 Align AF3872 Locked Open 2,500 1,000 0 6334-1 85-109 Inst New Cabinet in Ctrm 34,000 400,000 244,180 6196-1 85-154 Del SFRCS Opn/Clo Sig to Afiv 53,500 10,900 10,369 3835-1 85-157 Lover SFRCS Lov Lvl Trip Sp 5,000 30,000 8,604 3836-1 85-207 Replace CRDH Ventilation Fans 343,000 255,000 237,658 6352-1 l 85-264 Reserve Resource Selector SV 5,200 1,500 660 3846-1 85-273 Arts RxPvr Bistable Lamp Ckt 3,300 1,000 0 6334-1 85-333 Main Stream Vibration Monitor 44,400 5,500 3,958 3888-1 l l 86-021 Add Arts Alarms 15,100 2,500 17,131 6334-1 86-030 Rpr Pipe Support 40-CCB-16-H3 5,200 1,500 0 6336-1 , l 86-031 Add Limit Switch /Limitorque 227,400 203,000 123,626 3852-1 i 86-036 Inst RCS PI in Control Rm 67,500 75,500 123,626 6369-1 i 86-123 Reactor Pvr Auctioneer to ICS 27,300 19,000 0 5014-1 86-192 Repover Start-up Feedpump 324,000 300,000 161,070 6371-1
)
i l ESTIMATED ESTIMATED COST COSTS COST THRU CHARGE I MOD DESCRIPTION 1988 1987 11/22/87 ACCOUNT 86-201 ! MSSV & AVV. Posit. Monitor 150,000 250,000 77,566 6196-1 86-291 Modify HPI/MU Sys Flov Test Ln 30,000 150,000 19,779 6334-1 86-318 Relocate Hot Leg Monitor Sys 25,000 80,000 74,303 3866-1 { i 86-330 Improve AFV Level Control Sys 907,000 240,000 222,875 6334-1 ! 86-425 Relet All MDFP Local Ctrls 519,500 525,000 498,169 1 6372-1 i 86-432 M/U Feed & Bleed Capability 875,000 880,000 834,543 6309-1 87-037 Replace PG-43 3,000 3,000 0 6336-1 87-058 Sub or Strut for a Snubber 700 4,100 1,508 3903-1 87-063 Control Room Console C-5717 35,900 45,000 41,515 6196-1 87-064 Control Room Cabinet C-5717 21,000 45,000 41,751 6196-1 l 87-065 SFRCS Block Svitches 16,000 20,000 17,308 6196-1 l 87-066 Cntrl Rm Cnsi C-5706 L-5710 32,000 21,000 18,957 6196-1 87-067 Cntrl Rm Console Mimic Lights 36,000 45,000 41,821 6196-1 l 87-068 AFFT Dischg Press / Speed Ind 21,000 25,000 22,985 6196-1 } t 87-069 AFV Flov Indications 31,000 65,000 59,963 6196-1 l 87-070 Control Room Console C-5721 26,000 43,000 37,064 6196-1 ' 87-071 Cntrl Rm Pnis C5701,5724,5798 18,300 20,200 0 6196-1 87-072 New Control Room Console 5,000 4,500 0 6196-1 87-073 Control Room Console C-5717 11,000 10,500 10,112 6196-1 87-080 Re1 Temp Elements TE-RCR-2 17,000 25,000 0 3977-1 87-092 SFRCS/AFV Manual Initiate SV 26,300 37,000 33.502 6196-1 I 87-104 Mod FSk M-HSC-162-2-Al *
- 4 O D&!i 87-1062 Upgrade Sta/ Inst Air (Non-Out) 48,000 196,000 24,415 6377-1 87-1081 Rep 1 Batch Cntrl in MU & F Sys 8,900 4,800 0 6413-1 l
4 i 5 * * * * -. .
ESTIMATED ESTIMATED COST COSTS COST THRU CHARGE MOD DESCRIPTION 1988 1987 11/22/87 ACCOUNT 87-1085 Eli. CTRH Annue. FST Out FEA 22,000 0 0 87-1092 ICS/NNI Auto-Select Svitch 104,000 100,000 0 C 87-1093 MRB Direction Error Mod & CK *
- O 6334-1 87-1102 SFAS Channel Bypass Shutdown 9,700 2,000 28 3871-1 87-1105 ICS SG LVL Auctioneering *
- O C 87-1107 SFRCS Modificattons 3,250,000 250,000 20,894 6441-1 87-1108 Prov Reflash capability 10-2-7 8,000 10,0000 13,103 6196-1 87-1110 Prov Reflash Capability 1-4-1 9,000 10,000 3,742 6196-1 1
R7-1111 Prov Reflach capability 1-1-6 16,000 10,000 2,994 6196-1 j 87-1112 Prov Reflash Capability 1-1-5 16,000 10,000 3,716 6196-1 87-1113 Prov Reflash Capability 1-1-4 16,000 10,000 3,712 6196-1 87-1114 Prov Reflash capability 1 *i-3 16,000 10,000 3,939 6196-1 87-1115 Prov Reflash Capability 14-1-4 5,000 10,000 4,032 6196-1 87-1116 Prov Reflash Capability 14-1-5 5,000 10,000 2,868 6196-1 87-1117 Prov Reflash Capability 16-3-6 9,000 10,000 2,789 6196-1 87-1118 Prov Reflash Capability 1-4-2 9,000 10,000 2,027 6196-1 87-1119 Prov Reflash Capability 1-4-3 9,000 10,000 1,922 6196-1 87-1124 Inst Hosing CCV Stator Line *
- 5,254 3811-1 87-1130 Replace Pam Panels *
- O 6196-1 87-1138 Upgrade Sta/ Inst Air (Outage) 345,200 136,700 101,658 6377-1 87-1147 HPI Flov Indicator *
- 0 6388-1 87-1160 Modify Limitorque Cont Scheme 10,000 0 0 O&M 87-1168 Rep DG-RV13A&B & DH-HV14A&B 44,000 85,000 592 6414-1 87-1174 ICS Signal Limiter 20,000' O 0 3998-1 4 - ,
ESTIMATED ESTIMATED COST COSTS COST THRU CHARGE J MOD DESCRIPTION 1988 1987 11/22/87 ACCOUNT l 1 87-1198 Repl AF5996608v/9008 CL 2 Vivs 102,000 0 0 C 87-1258 Set. Starter for DH09B & DH09A *
- O 6388-1 l SUBTOTAL 10,506,500 6,369,800 4,282,518 Estimate Not Available At Present Time.
I 1 i l e 1 ?
. = . , . - _ _ , .. - .-,
05R IMPROVEMFRT MODIFICATIONS ESTIMATED ESTIMATED COST COSTS COST THRU CHARGE MOD DESCRIPTION 1988 1987 11/22/87 ACCOUNT 77-398 Change MSIV Bypass Valves 35,000 25,000 18,667 6204-1 79-229 Instl Flanges in Line HSC-117 6,900 2,000 0 3805-1 80-027 Inst Cage Ctat D-Ring 17,000 22,000 5,271 6216-1 81-062 Modify D/G Lube 011 Sys 18,500 5,900 2,294 6307-1 81-223 Hsr Bolt on Manvay Mod 225,000 12,000 11,888 3810-1 83-007 Repl F/H Contrl Rod Masts 203,000 20,000 1,584 6221-1 83-076 Repl Upper Core Barrel Bolts 50,000 179,000 4,623 6312-1 83-138 Replace SV-24 201,000 52,000 45,964 6233-1 83-164 Repl Obsolete Bailey Redr 82,300 42,000 29,706 6407-1 84-067 Refuel Reactor 6,995,800 10,000 9,183 3820-1 84-101 (Sup 1) RV Head Lif t Device 15,000 315,000 81,934 6246-1 84-104 Modify N2 System Elect Penet 14,500 6,500 5,376 3823-1 84-150 CB Polar Crane Safety cable 2,700 2,500 0 3946-1 85-024 Inst Remp React Cav Dosimetry 15,00) 38,700 14,062 3825-1 85-065 Align AF3870 Locked Open 7,000 0 0 6334-1 85-096 Redundant SG Lv1/ Press Ind 23,000 119,000 0 6196-1 l 85-143 SS 0-Ring SOR Press Valve 68,000 ! 170,000 160,147 6306-1 ' 85-245 AFPT Gov Viv Seat Drain 7,500 5,000 3,769 3843-1 86-038 Add Press Gauge Near NN-409 7,000 2,000 135 3853-1 86-063 Repair Degasified Vater Pmps 6,300 1 35,800 0 5014-1 86-137 Rep Gasket Drain 2,000 1,000 274 3860-1 86-157 Control Room Reheat Coils 14,300 2,000 192 3876-1 l 86-160 Install Anti-Rotation Pins 61,000 2,000 282 3862-1 l 86-175 Replace Valcor Sv Springs 25,000 1 77,000 2,325 3863-1
-48
ESTIMATED ESTIMATED COST COSTS COST THRU CHARGE MOD DESCRIPTION 1988 1987 11/22/87 ACCOUNT 86-200 Anti-Rotation Pins for MSSV's 3,000 1,000 0 3868-1 86-251 Replace CCV Stop Check Valves 95,000 5,000 0 C 86-263 Replace PSA Mechanical Snubber 219,000 25,000 10,577 6370-1 86-328 (Sup 0) Replace PCB Non-0 Xfar 137,000 130,000 122,963 6276-1 86-346 Cool Tvr Beam /Sup to Drf Elin 5,600 25,000 ?.2,729 3908-1 86-372 Remove LFC CKT from ICS 4,000 0 0 D&M B6-376 Repair Support 20-HBD-86-H17 4,300 1,000 0 6336-1 86-397 Replace Rectifier Flovmeter 3,300 1,900 0 3928-1 86-401 PI-RC2A6 Instr Ckt Design 15,000 5,000 4,310 3900-1 86-403 Instl CF-30 & 31 Anti-Rtn Dvc 21,200 4,800 55 3898-1 87-012 Repl Cond Pol Septum Tubes 58,900 182,000 110 6410-1 87-021 Rev Limitorque Lmt SV Numbers 1,500 1,000 982 3921-1 87-023 Install MFPT Thermocouples 15,000 10,000 1,626 3947-1 87-089 Repl Porv PPG & Supports 46,100 154,000 98,674 6303-1 87-1010 Przr Htr Adapters 122,000 20,000 83 3814-2 87-1011 Flov Instr for AFVP recire 18,000 5,000 0 6436-1 87-1019 Add SFAS Rad Mon Connectors 3,000 1,000 155 3953-1 87-1021 SOR Replat Due to Diaphra Mtl 68,600 60,400 0 3961-1 87-1025 Chng Screvs TB-4 in ARTS Cab 2,400 2,600 0 3962-1 87-1031 Instl Rod Stop Cire. 18,000 4,000 3,066 3804-2 87-1033 Rep 1 MDT-20 Position 5 Board 2,800 500 0 3965-1 87-1035 Redesign SG HYD Snub Load Pins 8,000 7,500 6,141 i 3803-2 1 87-1071 Service Vtr Check Valves 12,000 2,000 0 3955-1 87-1072 Service Vtr Check Valves 7,100 9,100 0 3805-2
-49
l i i ESTIMATED ESTIMATED COST MOD COSTS COST THRU DESCRIPTION CHAIARGE 1988 1987 11/22/87 ACC: COUNT I 87-1073 Service Vtr Check Valves 9,000 12,000 107 3EtB06-2 87-1074 Auxiliary Feedvater 1,800 22,000 19,745 2DF07-2 87-1075 Cntr Ra EVS SV-130 & SV-134 5,400 12,000 379 3BtB08-2 87-1076 Service Vater Check Valves 9,500 13,600 3,817 38009-2 ; 87-1100 Rep 1 Obsolete Baily Instr 3,000 i 2,500 1,677 O&M 87-1101 Remove BTU Limits from ICS 3,000 5,000 3,085 384145-1 , 87-1104 Remove ICS AFV CKT 10,500 3,000 1 0 393'59-1 87-1141 Cire Breaker Fall Prot Trip 22,000 15,400 l 0 3974-1 G7-1142 Gen Trip for Stator Grnd Fit 18,500 13,300 0 39 "75-1 ! 87-1155 Add Snubber to MSSV EBC Line 14,000 11,000 1 0 501G4-1 87-1161 Modify Cooled Cond PPG Conn *
- O 87-1164 Turbine, Gen & MSR MODS 7,062,000 0 0 64x25-1 87-1166 Total Flov Controller Removal 8,000 0 5,254 \
38101-2 l 87-1182 DH2733 & 2734 Guide Mod 22,000 0 85,043 63E2B1-1 87-1193 Replace Existing Pass System 208,800 120,000 0 3812 3-2 i 87-1195 ECCS RM Sump Pep Piping 26,000 22,000 0 37-1273 Aux Feedvater Pump Turb *
- 0 87-1286 Enhance M.S. Press Relief Instrum *
- t O
SUBTOTAL _16,518.000 2,223,600 800,142 ' TOTAL 27,024,500 8,593,400 5,082,660 Estimate Not Available At Present Time.
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Toledo Edison /NRC Meeting June 26,1987 a lntroduction a General Status and Summary of Accomplishments a Personnel Changes a Major Toledo Edison Commitments a Resource and Commitment Review Process a 5th Operating Cycle / Refueling Outage a NRC Support
l i 1 l i Fifth Refueling Outage ! Planned Activity by SRTP Systems 1 1 l l l l
- e l
5th Cycle / Refueling Outage NRC Commitments Current Work Scope Summary: Projects 147 Studies 94 Programs 10 Procedures 42 Preventive Maintenance 17 Other 85 Totai 395
9 I 8 Tasks Planned For 5th RFO Completion Design / Material / Procurement may not support schedule. m Feed and Bleed Enhancement. m Auxiliary Feedwater Flow / Steam Generator Level Controlimprovement. m Replace Station Computer Multiplexer, a Install Additional Safety Grade incore Detectors. m Replace Neutron Flux Equipment. a l,nstall Leakage Monitors for MSSVs and AWs. t l
Steam and Feedwater Rupture Control System (SFRCS) a Remove automatic close signals to AF599 and AF608 and leave valves open to improve overall reliabilityof AFWSystem. m Modify SFRCS to preclude isolating both steam 9enerators if coincident low pressure signals are received for both steam generators. ; a Evaluate modifying control circuitry for main steam isolation valves to improve reliability, a Evaluate several additional changes to SFRCS to i improve system reliability and improve decay heat ! removal capability. m Evaluate additional improvements of Control Room annunciator indication of SFRCS actuation. !
- Evaluate removing SFRCS close signals to l atmospheric vent valves, l a Establish improved record keeping for SFRCS power supplies and trend to better determine expected service life.
m Monitor, periodically, the 125 Voit DC bus to ensure noise is at acceptablylow level. 1 i i
I Auxiliary Feedwater System ! i t a improve steam generator level control capability l when using AFW pumps. m Install cavitating venturies to limit AFW flow. m Evaluate potential for contamination from Service ! Water System to AFW pump suction. ' e improve operability of manual mechanical overspeed trip on AFPTs. e improve access to AFW pump #1 room. e inspect intemals of AFW pump and turbine during 4 next refueling outage, a Provide accurate means of monitoring AFW pump recirculation flow. e improve AFW pump rooms ventilation control. i e improve Control Room board control, indication and reset layout. l l l l 1 4
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l Auxiliary Feedwater System (Cont'd) e investigate means to enhance local manual control of AFPTs. l a lnvestigate means to provide remote reset of AFPTs. t a Remove interiock on AFPT which secures turbine l on low suction pressure. ! e Provide an open signal from the valve control circuitry to AF599 and AF608 to prevent inadvertent closure. , s Automatic closure for AF599 and AF608 will be removed from SFRCS.
- Align AFP normal discharge valves AF3870 and l AF3872 to be normally open.
i t l l il I _ _ _ _ _ _ _ _ ._ _ - - _ _ . . -.------.-- - -- -- N
l Integrated Control System I Non-Nuclearinstrumentation m Evaluate attematives to rapid feedwater reduction , control scheme, a improve preventive maintenance system. I e Improve proportional and integrating module i response. I e Provide monitoring capability for selected ICS parameters (diagnostic). m Replace power selector switches. a lmprove transfer capability for pressure inputs to ICS for turbine bypass valves. l
l l l Main Feedwater System a Perform overall reliability study of main feedwater system and associated support systems. s Evaluate modifications to high pressure drain system to minimize flashing and vibration. l
= Repair or replace level indicating sight glasses on high pressure feedwater heaters. I e Correct variance among MFPT turbine speed indicators.
=
Improve reliability of MFFT tuming gear system. e improve flow control during feedwater cleanup operations performed prior to each reactor plant startup. I 1 l i
l l Main Steam System ' sInstall MSSV monitoring system. e improve mechanical design of main steam isolation valve position switches, a Monitor and evaluate MSSV setpoint changes > 3%. m PM program will be developed to inspect all six Turbine Bypass Valves during next 2 refueling outages, a Install modification to provide turbine gland seal and air ejector motive steam from both main steam headers, a PM program procedures will be developed to ; inspect all components of the AW strings that are susceptible to corrosion.
- Provide position indication for MSSV and AVV coordinated with DCRDR.
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1 Makeup and Purification System m Repair / replace leaking reactor coolant batch makeup flow control valve, MU39 (currently isolated). m Repair / replace batch controller. m Repair minor oil leaks on makeup pumps. m Evaluate and repair leaking valves MU19 (RCP seal injection valve) and MU216 (RCP seal injection bypass valve). m Evaluate and repair boronometer.
- Perform review of problems with hydrogen system (for maintaining makeup tank overpressure),
a Repair MU1903 (Cation domineralizer inlet isolation valve). I a Repair / replace seal injection stop check valves, a Replace letdown block orifice. t s improve communications capability bett;::a l makeup pump room and Control Room. I a Evaluate intended function of boron permissive light. ! a Perform review of failure modes of makeup system ! equipment (e.g., power supplies) and ability of operators to recognize problem and take corrective action. i 1 I 1
l High Pressure injection System a Evaluate need for design modification to HPl pump component cooling water stop check valves to preclude "sticking". m Calibrate HPI pump motor temperature instrumentation. m Eliminate low flow nuisance alarm on HPl pumps, a Replace improper flow measurement orifice in HPI
, pump 11 minimum recirculation line.
a lmprove communications capability between ECCS rnoms and Control Room. a Resolve means of leak testing for back-to-back check valves in HPI discharge valves. i 1 l
,l
l l I Decay Heat Removal System u Evaluate possible system modifications to preclude decay heat pump suction overpressurization. m Ensure spare parts availability for SWST recirculating pump and heater. m Evaluate alternative means of precluding over-ranging of low range decay heat pump suction pressure gauges. a Evaluate more easily read oll ievel Indicators for decay heat pumps.
= improve preventive maintenance for pneumatic valves DH13A & B.
a lnvestigate means of improving disk seating for check valves DH76 & DHT/. I l
.-._..,,-.-,,..---,,,-,,.,.,-_-,n~,,__,._
i Control Room Normal and Emergency Ventilation Systems e install flow modulating control valve in service i water cooling path for EVS. a Further increase cooling capacity of EVS. s Limit use of manual switches on local control 1 panels associated with EVS. j a Perform air flow balance of normal verMion system. ' i e Review overall adequacy of normal ventilation
- system.
4
' a Develop improved preventive maintenance ;
procedures for entire system inciuding dampers ! and actuators. a inspect and refurbish air handllrg duct work and ' associated insulation, filters and differential pressure units to improve cleanliness conditions in Control Room. j u Improve operator indications and control regarding l normal and EVS p.'Jon. ) e Clean and repair humidification system. Evaluate - attomate designs. j 4 u Evalusto causes of failures of chlorine detectors and station vent air particulate monitors.
I Control Room Normaland Emergency Ventilation Systems (Cont'd) a Revise the design basis for CREVS in the USAR section 9.4.1 including tables 9.4-1 and 9.4 2 (lR 8540).
- Prepare a surveillance test to provide periodic testing which will verify CREVS operability (IR 8540).
s Revise CREVS refueling test to include a cooling capacity verification on each CREVS unit. l l 1 l a l _ _ _ _ _ - ~ ~ -
ll Service Water System a Periodicelly ultrasonically test selected portions of Service Water System. i a Review service water pump shaft performance post-modification. a Evaluate apparent increased head and flow on I service water pump 3-1. ' s Evaluate tube corrosion / performance in ECCS room coolers.
- Modify containment air cooler valves to improve stroke time.
e inspect tubes in component cooling water heat exchangers. e improve temperature control for Component Cooling Water System. 1 j 4 1 i
l i 1 ll 4 i Station Air and Instrument Air Systems s Perform engineering study of Station Air and instrument Air systems to evaluate several areas for improving overall reliability e.g., required emergency air compressor (size; isolable vs. non-isolable loads; need for 100/100 psig regulators; leakisolation flexibility).
- Install moisture trap on SA28 to improve draining.
' m Segregate air intake and diesel exhaust for diesel air compressor. a Modify Station Air and Instrument Air systems to I prevent dumping system air to atmosphere when l the dryers are bypassed. i e increase frequency of dowpoint check on instrument air receiver to detect unacc6F4mble moisture leakage from station air headers to Instrument air headers; install permanent air dryer i around IA408. e install flow meter to permit trending of air system
; degradation.
l I 1
- i l
l Containment Air Cooling System and Hydrogen Control System a Confirm flow balancing of Containment Air Cooling System. m Replace failed totum bend on cooler C11. I a Evaluate instaMion of flow meter in purge test line to facilitate performing surveillance tests, a Install soft saat for vatve CV210 (containment ! isolation check valve). , a Confirm IT/drogen recombiner is compatible with l Davis-Besse system and can be made operable within required time. l
- l i
j i j ) l 1
a b d _4 i Component Cooling Wisiter System l s Add CCW room ventilation fan periodic test. s implement attemate pressure control for CCW surge tank. m Fix small oilleaks on CCW pumps. I I r i
1 l Safety Features Actuation System a Evaluate attemate surveillance card design. a Isolation Evaluatevalves, elimination of SFAS closure of main steam l i a investigate spurious SFAS Irmident level 1 trips due l to spiking of radiation monitor strings. ' a lmprove human engineering considerations
- associated with relative location of SFAS manual '
trips and associated reset pushbuttons (2) location i of reactor coolant pump sealin retum valve control switches. jection and seal I l l l
Steam Generator System a improve reliability and accuracy of steam generator shell thermocouple temperature readings. m Evaluate modifications to condenser steam jet air ejector radiation monitors, a Evaluate the use of S/G drains and tube rupture control crtteria to maintain the S/G level below the main steam line connections during a tube rupture. 1 I ) )
i i Reactor Protecthon System a Evaluate Technical Specification change to permit placing a defective channel in manual bypass, a Evaluate providing more reliable power range signal to Integrated Control System. ' s Eliminate noise spikes in NI Source Range channels apparently due to door alarm switches on RPS cabinets, i l I l 1 l i i i
l Post Accident Sampling System a Evaluate altemate PASS isolation valve designs to ensure adequate isolation a Submit response to NRC on their post accident sampling system safety evaluation import.
- l G
f
Gaseous Radwaste System ) a Eliminate air inleakage to Gaseous Radwaste System.
- a Evaluate redundant oxygen and hydrogen monitors
' on Waste Gas Surge Tank and Clean Waste Receiver Tanks. ', a Improve nitrogen overpressure control on waste ' gas tanks. m Obtain reliable operation of degas!fier. l m Open item 84-30-02 Vent Stack Monitor Sample Streams are to be directed back to origin or to radwaste. l 1 i l 4 I c ; i 1 a i l , a l
l 1 Reactor Coolant System ; e Repair end plugs on out of-service pressurizer heater elements, a Repair / replace nitrogen regulator for RC drain tank. m Repair / replace Tave digital readout. m Evaluate RC pump seal or motor parameters to be used for securing pumps, a Calibrate RC pump vibration instrumentation. 1 m Modify pressurizer heat bank operation to handle i larger heat losses. e install and declare operable a reactor vessel head i mm. i a Exercise the PORV at reduced pressure during plant shutdowns.
- a Prwide extended RCS F'esure instrumentation l I range greater than 2750 PSI.
i a Submit response to generic letter 8706 on periodic ) verification of leak tight integrity of pressure j isolation valves. i e Upgrade EP1202.01, Emergency Operating Procedure to include enhanced instructions to operators on the use of hot leg RTDs and incore i thermocouples determining subccoling margin l and norrnal circulation. . 4 4 l l l l l
l 4160 Volt AC System e Review consequence of paralleling bus tie transformers out of phase. ' a Visually inspect all 4160 Volt breakers in "Q" cubicles for "E'Mng damage. a Control nor#'Q" 4160 Voit breakers to ensure they j are not utillred in essential applications. , ' l
' s Provide improved control of circuit breaker and relay setting records.
l l i i i I i i i l i
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f e P 480 Volt AC Distribution System ' s Evaluate removal of stab withdrawal interlock feature, a Evaluate attemative means of providing ground feuit protection for 480 Volt AC motor control centers. m Establish program for tracking limited life componeds in motor control centers, a lmprove preventive maintenance on switchgear cabinet door hardware and gasketing. 1 j i I l e i J i
~. - -_-- -
I 13.8 KV System e improve method for racking in/out of 13.8 KV breakers. ; e Repair small oil leak in Auxiliary Thansformer. I I l l l I l I I
250/125 Volt DC System a improve tempemtum control in bettery room, a Evaluate design change for low voltage miays to reduce failures. I i I o l 1
\
120 Volt instrument AC Power , a install ventilation fans for inverters, a Evaluate Installation of static transfer switches . and/or tank circuits to reduce potential for losing l an inverter when a ground fault occurs, ' i )
, 1 1
l l i i i 1
J i Security System a Perform waluation of several operational /reliabilh improvements for securtty W, l 4 1 l l I l l s 4 I l l -l I l i i 1 1 J J l 1 i
l l Incore Monitoring System l u Improve reliability of incore neutron detectons for 15% to 30% reactorpower. m Evaluate need for two incore instrumentation multipoint recorders. l l i I l l 1 I l
l 1 4 Containment Emergency Ventilation System a Provide protection for instrumentation controls for ; fans.
)
e Revise procedure to ensure heat loads are addressed during plant modifications. l l
l l l i Emergency Diesel Generators a Evaluate improvements to diesel generator air start system and improve reliability of air compressors. s implement improvements for emergency diesel fuel oilsystem. m Replace cooling water flow gauge, a Perform evaluation of overall improvements to i diesel generator air intake configuration. l 8 Improve diesel generator speed and electrical i frequency controlcapability. l m Correct erratic bearing temperature indications for diesel generators. ; m Provide corrective actions addressing violation i regarding inoperable EDG and subsequent failure (IR 87-04 02).
O .O I l Control Rod Drive Control System a Evaluate attemate control rod direction error circuit design. m Evaluate control '~od motion momentary interrupt circuit. l e Review overall service structure cooling design. m lrnprove power cable mating and handling procedures, a Evaluate use of higher temperature silicon power cables, e inspect all control rod leaf spring anti-rotation devices at each refueling outage.
- Evaluate improved control rod drop time test techniques.
- To preclude low voltage problems, check voltage output of CRD transformers frequernly; clean and Inspect Inductrol voltage regulator and lubricate motor generator set every refueling rArtage, a Determine long-term resolution o' CRDM nozzle flange leaks.
l l l l l
---,,,-,v-.c --,,-- , . - - ,,
Anticipatory Reactor Trip System l a Modifylamp test circuit. i a Provide labeling to minimize problems in correlating channel and breaker designations.
l Other a Revise shift tumover checidists. m Review Bechtel calculations on Test Piping Analyses. m Upgrade STA qualifications, a Expand training on containment isolation valve requirements. l l l
SRTP ltems with Post 5th RFO Completion Schedule 250/125V DC - Evaluate alternative methods for ground fault detection. l 4160V - Review consequences of %. paralleling bus tie transformers "BD" and "AC" out of phase. 480V
- Investigate feasibility of installing ground fault protection on MCC circuits such as heater circuits.
Anticipatory -Investigate separating ARTS Reactor Trip channelsignaloutputs to the System computer.
-Investigate EHC pressure fluctuations while performing turbine stop valve testing. 3 t
Auxiliary
-Investigate use of a manual trip Feedwater System lever on trip / throttle valve linkage for easier tripping.
- Conduct study to determine means ofidentifying water or condensate in auxiliaryfeed pump turbine steam supplylines.
1 l l
I 1 SRTP ltems with Post 5th RFO ; Completion Schedule (Cont'd) Control Rod Drive - Review control rod drive venting procedures and install quick i disconnects on CCWlines to i minimize water spills.
- Evaluate attematives for service structure cooling design.
Decay Heat - Add Control Room annunciator l Removal for BWST heater outlet temperature. Evaluate heater system forimprovement.
- Repairleaks or replace the cyclone separators on DHR pumps (seal cooling).
- Evaluate potential to eliminate sealed pit design for DH11 and DH12.
1
l SRTP ltems with Post 5th RFO l Completion Schedule (Cont'd) Heating, - Evaluate performance of Control Ventilating and Room HVAC after rebalancing. Air Conditioning - Relocate controls and conduct l study for optimum humidity control for ControlRoom normal air conditioning liumidity system.
-Install Control Room switch for recire mode air conditioning.
Integrated Control -InstallsignallimitersinICS System proportional plusintegral controllers.
- Evaluate ICS cabinet cooling.
-Investigate tmnsfer signal difference between steam generator pressure and steam heade/ pressure. l Main Steam - Evaluate noise / vibration on !
steam admission leads to turbine i as a result of full are admission.
- Evaluate need toinstalla valve monitoring system capable of l identifying valve lift setpoints.
l l l 1
, _ _ _ _ _ _ . _ . . , . - - - - - , - - - ~ - - ~ - ' - ' ' ' ' ' ' ' '
l 1 i SRTP ltems with Po.st 5th RFO Completion Schedule (Cont'd) Emergency -Investigate miocation of existing Diesel Generators temperature switch orsolid state replacement switch for bearing temperature readings.
--Increase frequency for temperature selectorswitch cleaning.
- Place a Hear-Here booth over the Gal-tronics in the diesel generator rooms.
-Install air cooled aftercoolers with separator.
- Evaluate need to replace / repair ;
existing dieselaircompressors. i
- Add localoverfillalarm on diesel fuel storage tank. Change low levelalarm setpoint from 38,000 to 35,000 gallons. '
High Pressure - Finalize cyclic fatigue limits for Injection HPl system.
=
SRTP ltems w'ith Post 5th RFO t Completion Schedule (Cont'd) Makeup and
- Review batch contmilerand Purification determineif replacementis System required.
-Investigate boronometer operations.
- Review Hydrogen system.
- Review consequences of MU32 failure positions.
Reactor Coolant - Review methods to enhance System
- reactor coolant drain tank maintenance, i
-Install new corr; exit temperature indicators.
-Installlowlevelinteriock for use of pressurizer heaterbankin manual.
Reactor Protection - Evaluate need for more reliable System power range signalto ICS. SFRCS - Replace steam generatorlevel meters.
-Insulate steam generator shell thermocouple openings.
Waste Gas System - Evaluate relocation of oxygen and hydrogen monitors for ALARA concems.
_.__-__..-.1&.' '
* . L~n , . -
INTR,A.C,OMPANY
,o u MEMORANDUM NLD-87-00200 TO
\ s Distribution
- - - . - . . . - - - . - i
\
T. J. Myers, Nuclear Licensing Director / - sugater ~ Fif th Refueling Outage Commitments LDC 87-232 CC-6.1.4 Distribution: hT. L. F. Storz, Plant Manager P. C. Hildebrandt, Engineering General Director L. O. Ramsett, Quality Assurance Director M. L. Stewart, Nuclear Training Director B. R. Beyer, Nuclear Projects Director This memorandum provides updated lists of:
- 1. Commitments specifically made with the NRC via docketed correspondence that are to be completed between now and the end of the fifth refueling outage.
- 2. Those tasks which we are currently planning to complete by the end of the fifth refueling outage. Included are those that are part of the larger, overall Course-of-Action commitment for the conduct of the SRTP, These tasks were discussed with both Region III and NRR during June 1987.
The Engineering Division has concurred that tasks assigned to Engineering are currently planned and scheduled to be completed by the end of the fifth refueling outage. By September 4, concurrence is requested from other Division Directors that assigned items in the attached lists will be completed by the end of the fifth refueling outage based on current planning. We intend to share the contents of these lists with the NRC to reach agreement on the scope of the fifth operating and refueling cycles. We will inform you of any changes to these lists resulting from our discussions with the NRC. Future modifications to the attached lists will be made only with the concurrence of the cognizant Division Directors. TJM/PCH/bjs Attachments cc: D. C. Shelton G. M. Grime J. K. Wood D. S. Knaszak S. C. Jain E. M. Salowitz J. A. Chlapowski J. A. Doiron G. A. Gibbs Nuclear Licensing Division Personnel J. L. Scott-Wasilk Nuclear Records Management w/o M. E. Schefers D. R. Lightfoot
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- , , FIFTH REFUELING OUTAGE EXECUTIVE
SUMMARY
SEPTEMBER 1, 1987 PAGE NO. I INTRODUCTION 1 II CURRENT SCHEDULE DEVELOPM W 2 - 15 III SCOPE OF VORK (MAJOR ITEMS)
> a) Total Defueling/ Refueling 16 - 17 b) Plant Modifications 18 - 31
- 1) Licensing Requirements
- 2) Improvements c) Turbine Generator Vork 32 - 35 d) In Service Inspection (ISI) 36 - 38 E) Corrective Maintenance Activities 39 - 40 IV MANPOVER PROJECTIONS 41 - 44 V FINANCIAL (PRINCIPAL COST) 45 - 47
- 1) Capital
- 2) Operations and M;1ntenance (0&M)
- . = _ _ _ - - .. - -- - - . - -- - . . - . - - _ . -
n INTRODUCTION b w .>.
. The current ~ schedule calls for Davis-Besse to conduct a reactor refueling during the first quarter of 198.8. In addition to this
~
major activity we vill also accomplish a number of other work itees requiring the same attention to detail. In orde rto fully
" ~ appreciate the significance of each work ites withis a refueling.
framework," the nope of eacT Vnk ites'v111 be 18Etified and a _ states,given in thir summary. go .
~
The following objectives have been established for 'the fitth Refueling Outage-
.+
Total defueling/ refueling Completing all licensing required modifications . Completing a large number of plant improvement ' modifications Completing a major inspection and overhaul of the turbine generator Complating a scheduled In Service Inspection (ISI)*
, Completing all outage related maintenance work orders (NVO)
Performing a required Integrated Leak Rate Test (11JtT) . ., . aw . ' L
- A review of Jthe above objectives and'an understanding of the scope . i of work related to each iten desufles a "full plate
- for~ the current scTetuled outage time f rame. A close partnership will be j
~
required Mveefall groups at DavislBesse associated with the 5th ' Refueling Outage in order to achieve,our stated objectivas. The key to this-refueling outage ' performed on time and within budget, 1 will be the proper and thorough Plannias, coordinaties and timely , reportina of preWress and problem identification prior to and during the outage. In order to continue to improve and build on
~
our alreakies'teblished capacity to manage successful outages at Davis-lesse; an executive suonary becomes an important tool e% o!iering'neangeousle*geseh-aeusee ei lafonentiosacheseby.the- .-- current scope of work, identified concerns and available resourcee l
+
can he' projected and any trends noted. '
*' +*
l It should be understood that a large body of thl information vill and is. changing due to a multitude of concerns, therefort, this i
- c' ^'
summary vill be updated every two weeks until the start of the 5th i Refueling Outage. 1 Most of the information presented in this summary will take the form of a graph or chart providing a visual framework, thereby - l 1essening the amount of time required by management to gain *
- insight into the many items presented. *
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TurbineGeneratoractivlugs , Toledo Edison has received the, final bid proposal submitted by G.E. for j' the SCturbine/ generator work.' A meeting to discuss the contract will* j be scheduled for Mid-Sepiesber. - ,,
.n s,. The.468p' site Aeprospntg ivt. reported on August 24, 1987 and is*
presently completing requfred~ditW'Traint$ egep vm . t cision is M D run .le ,' tine ' Turbine -
-A 'schel d :.s
' * * 'to spa feast This~tiest requires a se ~ -day plant shutdevn and sust be'peMerced to identify the extent of york to be done on the Lov ~
' -- . ua
.. s pe g ure Turttaes during SE outage.
n, .- 4 _ . + w Feel ] " - % tivitiest,3,,.ie m,g, . , .,
- s. > + Performaneewd Nuclear Engineering have chosea October 13, 1987, as the dat's to start receipt of fuel contingent on SW confirmatieg. The
^ fus13 sad control cocponent receipt vill take approximately' nine weeks to complete.' <>
e"* - The decistori has been reaffirmed to trr the Upper Core Barrel Solts in the Fif th Refueling Outage with repiscenent as a contingency only in
"' . ateer$ce with the Projoet Plan. Lietted 14ver Core Barr'l e Bolt UT i
Inspectica is also planned in the Fif th Refueling with a decision by
! -- 'the M pending additional Entineering input est its teeling y Fabrication in 1967. Decision is still pending on the performance o1 the ARTS Inspection-in the Fifth Aefueling Outage while the plant is N . #",'defaded.' 'Ine present ,ecesoele % analysis.any met justify detag ARIS ' <'
in ' -
+ ,,. the Filth, Refueling. .y
^p g m 15t M vitt'es
/-
pre - % m. .g p p , ,, ,,
^ , The
, con tual and. detail planning ~et the IsI activities to completed g # ,, .: ' las These
.th the exce ten of the ressure/h dro ties are ava ting identif$aation bylTelli
'medyi,tigem g;
i ~.3
, . . * ,/ ( tagi ~ ' ten Engineering is reviewing tha rMuirements for the perto f OTSG secondary sudiP5thble-tes'tIW.~ Thirmust be
2
" ~~ required _ performance of ARIS. ;As a contingency, a required , ~
eheftals et and
. 4 ./, detail planning ~of the unck has beia accosplished. ~ ~
,. . -~% w. . -
A liiig,47discusithe ,y ISI support craf( requirements vilDbee h'Iin -
- ~ * Mid-September. = ,y ,
r r W~ , , m -"INT $tivitiest %
- Outage Management has provided the Plant Manager with three 11AT "schedule scenarios to aid him in making a decision 04 an early, late:or during refueling 11JtT performance. The tentative plcn is to perfors i V I the 11Jtt at the end of outage.
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i f Forformance Engineering vill revise the procedure st 5061.01 upon receipt of information from Design Engineering (RFA 87-778). This~ RFA is expoeted to be supplied by 9/30/87. Dewpoint and flow meter instrumentatGn vill be shipped off-site for
! v- es&&braties in Mid-September, sed will:ba peturned just prior to 'the ILAT '
l start date,,once that date is determined.' g was p , m eo - - my' ' w . . 4-' .. z., % w Staties Banes 78
\ W The rewrite of station battery specifications (3180) was completed and 1 -
approved en Aigust 26, 1987. This approval date vad ten days behind last months forecast date. Due to this ten day delay, the purchase
- - . - order for"procarenest of the replacement betteeles asu the bettery receipt inspection plan cespletion dates have been de,ayed to a SeptembH 15, 1987, this will impact the projected March 1,1988 i . delivery, date, due to the battery supplier lead-time estimates.
e * :. Bechtel is no. longer involve'x .d in the development of the DC Load Table
<by mode. A' study is in progress by'the Independent Engineering Safety
! Organisation. The results of this. study will be evaluated by Systems
*'and Design. Engineering and a DC Load Table vill be developed. This
'- activity is projected to be complete by December 1,1987 and will not
- have a' direct,tapact on the SR battery replacement. - 4 Fire Protecties &ctivities: , i a '
) -~ "The WorkseopY'Osanittee end Licendag have reviewed the fire pielection I
commitments and determined that the commitment to complete this work
- % ,' vill be differed until ,the 6R outage. Because of the clarification as
; (a commitment, the Fire Protection section of this report has been
- ros this g report..
]
. % remo d
% hebber N t1M nnas , :n. w,,c % .
~
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.- w--
n- s y .
. wWhaintennace had ande the decision to rebutid the six 20 inch _geen
; generater snubbers. The material l'or the snubber rebuild was ordered ZM .ea**..,
in e 'the'5R out July, as required. This allowed maintenance to ident! y the u work, whteh tire &ks down es follows: 300
'" .m seu are to be'v1 "1 ted,110 sadl bere hydraulic' l ^
i da,be rebuilt duq tos'even year seal Itfe replacemat
^N a requirements. Na%cf sle> der" the rebuild has been ordered.0WeWis an l os goin(effort to identify those soubbers'that can be repliced non-i ,,
*-- outage under action statements to lessen the outage imp".ct. Also in '
3 the scopWie the replacement of approximately.110 odanical snubbers j vith pre . tested,' drop-in small bore hydraulic snubbers. A vendor has ! been selected and material ordering is_la progress.
- m i
- The snubber test machine computer software enhancement is being i persued, even though compli tion with the vendor have developed.
Maintenance I.as stated the f the machine isn't back la time to'
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,Y support the out44 it will not impact the"snubber verk beefuse an '
v alternate snubbwr test machine is on-site. l l _ Preventative Naistensase ,.'
'm# completion of the 'PN Standardisation Effort' has oli from i d' '# '
,1987 to September 15.,1987. ,This.prograa vi$ .e - 1 l '"r se PN's.but does not affect the SR outage FM vorkscope. l 1 ""
P t ,stenance end.5pgem peopfag.) ave completee.a review. w l ks thatare refuel / tug ne generator outage'nlated. ! e Presently, 754 FN'i'are identified as. outage related and aradditional l 58 activities vill be 'oubmitted through PMAA/PlWD review for ' l reacheduling or crediting. 1,ong-lead Mi asterials havrbeen identified and DON's submitted. Approximately 150 PN's still require material to '
,be ideadf.ied by,8ystes Angineering and -DON's submittedr"' - u ,
,e m
- Procedure NEP 074 training is continuing with the completion by"the '
last' student delayed to September 15, 1987. Equipment trending, data l collection is in progress and is now an on-going program. It 'is'aet
, expected to affect the scope of the SR outage and will be removed from i
.the sthodule.next month. '
f e Notificaties Activities
, p The present modification report better defines each project's impact upeaJha Fif th Refueltag Outage 'as a vbole. N intent of this i
y analysis is tc further prioritise projects and effectively,pe resserces. (y *M w nws. "% v y m schedule' depicts an advance et, required target dates' bas'Td on an l ently January outage start. The current forecast dates deph't a
%~ ch
. costfeelaig'ev~erall ellestone schedule slippage. h slippage over the
.D_ 4e p-th' s.apprealsetely one week.91eptet ,te the 54,0utage,4p a the Nodification Activity section of this reports '
- i y ' M W ng % _.-9::f, +
' + ws.y %, ,s ~n '
e .
-- Y/ ,tettal ma musb identified as soon as practica1'in order to l ob vender 3destings, annuals, hardean,*m,9terings and " ^' -
l 7 v - will provide the needed aformaties for nov
' ' '[ '
M I n$4 h h as they rol to t Outage ti2e'nling Commitments, ' '
# taern,.g 7 mdeal;mainly withcategories, the hanger,,reviWyrogr he ellows:llguaggt **types
, q ,. .
< fa1Liste urges and are as <
__ a .. e- , . l % NCRs that are drawing change only. - This group is the
~ .
- majority of the existing NGLs. -
j w "m
' Nots and PCAQs that are in Engineering for disposition, n of.which operating cycle work may result. *
- V
- ecAos the hanger valkdown progras , generates that result p --- - W.rdfNW IKg ^ [ -** mv4 hyg . T, ,,
**' t' '. .
- n. .. -
4,. . i
pg .
*
- Y .a np 6; * ~ -
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m
^
in additional operating Cycle work. , Identified work items that fall both la the Operating Cycle and the Outage; The inspeetto.: of inforestion gathering area that
. .A ' em eassepasses K.9st.8e, (Additional Information Requests) -
in Containment and new valkdowns in the Annulus and w . ,,,p+ ~ Contre 1 toes, as theos earsaty.be performed daring er +-- -
<**w ,eutage.. ,
s s magineering hps issued a work-off schedule for both the walkdowns and l dispositions. Except for the Annulus, Containment and Control Room work, all walkdowns and dispositions will be completed by the end of
== -September and November,1987 1 respectively. This schetute vill allev *- - 1
# . for completion of all m. Non-Outage Ranger work prior te,,t..he st..a,rt of the ,
4 ,,,,,,, a*
.- m ens: There are~tvt, major areas of concern within the obtage l Tt:41f,..those are the,scatfolding requirements in the Annulus and l Control Room to perfore the inspections. h Annulus will need four scaffolds two hundred and thirty foot to be build and left to support any resultant work from Engineering's dispositions and hanger '
" inspections. The Control Room will require scaffolding over the
- control Roos operating consoles and stand up panels. This vill be critical and vill require a great deal of operations coordination h* ~ . iL, support.
.n y . ~
j
, _ \
14TS Activities ! v . . .".+
. W finali l6Aton/quantificahog of 54 1475 coenitments.is forecast to-
- tiemp1Rb ea' schedule *nagest 31,'1987. Licensi 's,prelisimarilistof.
l 5. 3 321;1 CTS itessesMagJedefiand. Approminate 150 are a
* - %,,Amt esanitanatet* An'essitlBal 165 LCTS items, ate y ammed heeempleties ~gna} MC foretthe.end'efp SE outage. This ki the total to.319 p '
- w^ tifientitia of-5R ICTS required pati 's 's forecast to ^ebbplete September 15, 1987.
4
. e ' i hs 54 NWO anfvo$t reMreelev and evaluattom for 3R vork %. _ l continui towards as esteber 1,1987 completion date.* Material is buing
~
F ordered is*Eenjunctlos vith:thefteeleW* tad pre of tha work +
,' Achages. All kaava eset packages required to su t 3R outage Activities"vill be complete by Octobet- 15, 1987 as schedulod c - l
- ~~u .. ap& 1 j ' --
The 8epletio,n date for the gpvision ist the DB5s Nvo format was extended to December 1,-1987 to allow for computer sof tware development. thin Jate implementation ^et the new Mv0 is not expected to impact worr. package' preparation as it continues into and through the C - 5R estage.
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Test Procedure Setivities a- + V Test review.et SR FCR/ MOD's continues as the detailed design is issued. ., c The development'ei the test procedures (ft's) began on' August 24,41987. Contir,ued slippage of the bulk of ,the FCS/N00 detail design impacts
'beth in review and TF development activities and pushes them into the
..., _ ,oetage.,3-fort m e Engineering has, hired additional,4est. personnel to assist in vrtWas and implementation of the TF's.
essaswysawm+ - ..
+ +- N c- '- ~
w-
%. For o ring issued a preliminary t procedure index in 4, Angest acheduled.' inifindex allove the tra ink of a TF fros its 59 elopment, testing and final review cycles. The index v111.
e .e initia
~
,, W updated perledically to include any nov information.
~
d'53ScheduleDe%$peesti c .- ,..
, o.q,. ' ,k cThe IStr. ARIf7u'pper/ lover corebolt inspectionar generic heatup & c -
cooldovn and power accession activities were incorporated into the SR
' ' ' f m.' s chedule. in Augg t . The scenario for the addition of the inspection of ^
M,,, .all and lower una core subsequentlybarrel bolts pushed removed as the directed outage by management.end date by eight weeks The scenarios" for the ARIS and ILRT activitier still require management decisions.
# Th(Ogtage ' Critical Path still remains through the T/C work.
%,+ '7
,*per The logic tie-in d!' over 570 kV0's was completed.last ' month in addition to the mEual additsee of activities for 18 FCR/M00's of which sufficient Engineering detail was not available to r'Jpport Actual Vork M. . ' "
- 4, Fackage yp Development.
m' wm ~as .*" 1 " Y'.]; fork will continue on input of the 1 dummy' FCR/ MOD activities througn l y Octe hr 1, 1the 'Approximately month of Se750 tomber to present a generated "Frelini,aary on Outage Sche 1ss- . PM MV0's are to be ' ~ l w ' v Q in Septemberballowing lished. " ; for the logic , tie-ia of those NUD's ,to bem
" l
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- p. n jw N2 gjl
- ing conce is the Pthe preseat rato
,, t'.r * ". :
Jocetiing,'Engineerlagy l i Y-M*h...g% i - 4- 1 oretsa j eqtion very date for qired esteri ose esterials, e tjed oes nokpisupporter g ths' lack of,h ' ' . I h . Y g- - e.g gg *
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4 ,.. - . . , , j -. . l FUBL MANDLING t.CTIVITIES 4 scope New fuel delivery dstes are planned as October 13.e .%
,through December 1. n is will include 8 ' Gray" APSRAs
'**musse- g.# N ' { and 64 BPtee w , ** enn e w
- w . ,
- Fuel loading 4 shuf be sc,, -s-heme vill be based upon M '_V '" reload report due this fall.a PP1504.02 (Puel/ Control w
Component Shuffle) vill 6 revised to reflect the MV
~
reload report. Se beload Report and License Amendment I Request will' be subeitted to the IRC on December.Ns** .,- -
. 1947. The expected date for the License Amendment (restart approval) ft6s: the NRC is April 25,"1908. Pk & ,
83-007 vill modiiy fuel grapples and control rod mast
'--* on the Main Fuel Bad 611ag Bridge. %1s CfMT w l - modification vill take two *teeks to implement. This '
work is to be performed prior to performing PT 5101.01 - (Fuel Bandling squipment Periodic Test). Current plans l are to impleseat FCR 83-007 on the Fuel Storage Bridge when divers are available near the end of September of
- this year. l
,,,,e
- Conctams: The RV pienus assembly when removed fo'r"tefueling is ,
staged in the deep end of the refueling canal. l Currently there is material free the RCP shaf t - .,,, i changeout la ;his area.
~
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m: f l e MODIFICATION ACTIVITIES - %.;e . - ! I g -
'~" ,4 $$ cope: There are curr Nt'l' y 3 21isodificitions IFC b ) s eduled,<
- in Project P/2 for ' development and implementation during' the Fif th Refueling Outa'ge. The total numbeE'of projected e
- l. , ,A , h *
'a a pd #
rt s a I t g A P '"**' * # t i d h t** k# g ~ "
- thro the h W1hdevY or cig g "scrutinising couldibe fth Operati q CycIv~. This pot 2ntial decrease in 1st * *' '
"'~ ~
'j' scope was ' fruitful with eight projects actBally .being #.' "
red 6 fined to the operating cycle. Bovever, th @ et gain g~. ~
". p ". " * * ' 4 'of.six I the Fifadditional th-Refdeling projects Outi@e7 presentbsa In'or elo sortiA ambi,gouN '
1 W.gw ^
- oi this .sqqpe, greater _,emphasissas been .dieec _ :toyergebid - "
, acre pre-outage modification work being comple in'the w- '** ,
operatingygle. demanding ?.The of earl r21 tap ease11ofcations o'f this,etra_tegy'_ engineering and aThderated" arej.,c, 4 -
-4 .. ,
procuresep of modification materials.:,,,er 4 " g Wg y 9,p % In addition, as areas o' f high outage activity gequigng ~ 9' extra coordination are. identified specialsTask Forces are
.e w' being formed to resolve the concerns and assure adequate # '
, integrationi of efforts are established.vene soch special .
V 'r. Task Force consisting of J. Johnson, R. Brubaker, N.4 i ^ ase 4, ,' p Borysiak J.' Bdr', J. DeSando, R. ZamenakiTR. Targer.and;,.
.'- #' ' ,' lead by V. Johnson developed preliminary,,ogt, age Jogidifor FCRs and100syhtch affect the control' Room an ares gt, N M'ird j .
. j ... s
.+
Righ --Outage Activity? 5 %
.m .- megy
.. 14 ,64 '," , ny + . . .
gM.c. +, % * * -.'
- Included vera all FAS,85GS,
- Motor ' Driven Ne,d.and B} # , . .e york, ICS 9 gm- HED (Human ing DiT9tt$socies). ontrol c%pt!Witief?8 and e
- w g' , p' "M dB&nges4 Logi les . t Plant . conditions've well as t'iiIs 3etween w0 :ectivities.3 t .'s t "
- i. , **'
e
'* "latigration '4fithid%sek',' liy"0etage svi$h &
Corrective Maintenance and other mechanical and electrical 4 * ' w T@k, w DeMimen t DW ton t rpo)*RoonNe t ed ou t@ . , ,q. , ! u .cs poin}ed out. the importance of obtainingmRqgineering i l
'@lkpackages
' outage plans.
'an34eceivink"materials'in time tT'iruppbrtge
"" Wh ,
.,. . Ag., .. s ,y ,, 1 4..:yy.
~ ,- # .
In this section you vill. find that modifications are '
~ '~
.. prgsented under two major' Headings: Licensing Required s,;~ %
Modifications and Plant Improvement NodificationeyThe L
- s. process of schedule inspact assessment and the results.
V the assessment is also presented under three major 4f , headings, none, minimus, and a coded definition of major - impact. g - -
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[ ,s l e k e s, 'OSR 1.ICENSING REQUIRED MODIFICATIONS w,d1W 4 7
,J '
~
nous"MTom' .. ngo ossmIrrIos)$P' 82-154*1 Replace:71've ~ to Improve Cu t
.ag '
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.ih
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#1 83-$ ReplaD,i' sher SF-Valves, x
~
- p. 84-002 RY H to Bot Leg Vent *
+p 4, ; . g ~ , m + - .
~ a A; ~.q- @~ @..
y 84-018 Rep 1 RC8+UA~lves ~~
- x #
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84-049 .< ,.InstSafety'GrheIncore mw we ', ;Qtt fp
.x @
4 14, w . , , . . "A +1gyn A
- m. su,go83 Rep 15It'taqMultiplexer a b . m
.+ .
%w c. ,h. 'M 06-101 (Sup1)RIBeadLift "
' f x,@
Device '+
*n" 84-113 Velen Check V1 Mods-x ...
'84-116
, g, (sup k Neut4on
- Flux x @ ,, '* .
M.*% .3
.w ~ Equipment
. , ~ . * -
. 44 3 ,.
% p_. w " %
, g ngg84-17A01 . p st Iso
'* x M' *
..a 6 AC108, 10$.e.s **'
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g e WM. ' ,, p f DeltoSFRCS 0 n/,g % g 4;([ ., x ,, n, ~ 4 Afty. f m - _
~ , _
.t w 4 ., 85-157 Lover SPRC8 % vi$1* " '*
x
'** g . Trip Sp '**
% ,ew -
. %' 4 . ;sPAsr -
,acW li V (SEE NOTES ON PAGE 31 FOR MAJOR IMPACT ASSESSMENT)
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. MOD N05B MINIIERI MAJOR
,- 'e.DESmIFTION "2 .
85-207. Replace CRDM Ventilaties - x@ r.M
' 7ans & ** + a
"*4 9 09 4eroute/Proteet Cables x b f. I 3., , . x "4l" m.
> g., . .w -n& ' j.e @' ) ^rve %Re h 8eledt # '
<**"' l
- g. .
***' 85-273 Atts Rx Pvr Bistable *t,amf'-'
x" ~ nt l l
. s ar; . v% y. . .,
- W W 933. Main-Stena Vibration -
x '~ ' - m.tg.A A v iage w , Monitor' .- 3., ,, *.* *v AM y Arts Marms Q ,~
.n 96-930 Apr. Pipe. Support .x. .
*-4 740-ccs-16-D3
, a . 2% . . . n w. ,
l 86-031 Add Limit Switch / x@ w ,, Limitorque
*ys...
86-036 Inst 1'ItCS PI in control x C. . ~*", ' # . t.,Q,, Roos . l
., 86 450* Add' Int'erlocks for Mov's x
# ' 'RdetorPvtAp.t&oneer l x l-..
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d.M$d's.. 86-2 g Repla Qtex/ d' Ins't -
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ga -
,, Ac)9t-w-86-289* Add Jumpers to TIBS % x
* ~ ^* M,. . *' ._ i 1
.,,.86 wf 91 Mdfy HPI/MU Sys Flov ,-- x l
, , g, Test' W k
,- . l 86 318 Relocate Hot Leg Monitor x
.~.
Sys
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s M00 DEsmIFTION NOME MININtNI ! MAJOR oc. ., _ W ~ 86-3301 e vs AFV Level' Control ... Ke@@
.~
A % y' y qi wa ,g .,*- '
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{ 46-3,25 11 MDFF 14 cal , ax. . s'% *
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WA 8'7-054 Sub of Nnst' for a x _4%-! r
- ~-
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- 4C-5717 A. - *#'~~4
.m , ' #"
!s;y. 4' 87-064'* Control Room Cabiset ~
x '@**
'*M y.r C-5717 37 p ,.. N w. , m.
- - )
.x @ ;
8 w ~ SFRCSflockSvitches
%* q' We 87-066 hentrl Rm Casl C-5706
,.. ~ x @'
,y # , d S kO67 ? Oifi b Console Mi le x@'
- ~
4-
%4.p.a %, ishts
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*m, ,,87-0927 SFRCS/AFV Manual #
l Init' late SV
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u A7-1081 Repl Batch Cntrl in MU & F Sys_ x
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~ NOD DESCRIPTION NOME ' NINIIRat MMOR !
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87-1090 Rep Anchor, x .. PSK-N-CCB-8-22-Al 4 .~
. ,,. e + 87-1091 Add Arts Alara x p p g 1093 MR3 m* a hw tionErro9 ,
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87a1102 SFA8 Chanhel Bypass -
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Shutdown ..._x ,
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g& %w-v t 87-1105.ICS .SG LVL'Austioneering
' t '~
l x Tast'T%y ;
%#N 875524' Inst"Eding CYttator Line '"x*
#' " ^' "~
^ ' N. ~ e
# % # -1187 $'Repisce;Faa Panels " * *
'x btA f#87;1138 Upgrale^Sta/InstAir ' 'E . , i m
% Ou tg **
- w Je , ., % .
87-1147 RPI-flow Indicator x
,, _ w e .,
'** 8' 87-1148 RSf1 BPI'Flov' Meters x
#" % -I
.. 4 87-1168 Rep DE-HV13A&B & W w . x y < 'g wg w pg.gy341gg
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. SGEDULE I.". FACT l
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DENRIFTION Nous --
. I n M <bi+ l
~.77-398 Change M8IT Bypass x --iy ~
w ;
;w ,, Valves . -
l w ,
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M' fg [*s.g 'N %t' # fD w ,
*s g., i h re , 80-02NInstCtk. Cage' Iring
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- # 1, . 80-02 > w..
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,j % z 81462": Modify +IMG tabe eth Sys . ,g.,ggut,qj . wff, sac 44kgqF # '99es*hgi217Mstl CopttCond es$1tngS ex ~ - h#
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he81-223 Mar Solt on Manvay Mot i X~~
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# Add Catel Ragp Indie x- ,
+ ,,, 83-007
- Rep 1 F/B Contrl Rod Masts x wo83-076 Apl., Upper Core Barrel '
x * ,, y
.y ~ *n.. So}ts ~ ,
j p p[~ s + 83d898 ' Regee -8U-24' g. - , y "'r p ..,'
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-058Mt Mt Trace Cables x . #
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'Y4 Inst gesp React Cav
" w x c % e-l s.
p Dosimetry - ', l +
'IN,, '# 'W %y l <,
g. 85-096 Redundant SG Ly1/ Press x 1 e ,gg w .~ 4
%/
85-120 TPCV Piping Modifications - - - - - x n... :( l
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% ** e N00 nu n TFTION BONE MINIMtal MAME 8S-194*[InstlTimeDelayinSFRCS x w 4. * .(7 -
* * ~ Leg .,
w ~ . , .
.v m <m 85-245 VAFFT Gov Viv Seat Drain , x 4.^ "%% pmsy g
~_px ~409
' iPress Gauge h y **Y l' 'M 4- M.. e 7
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y,y .+ 86 3 Repair Degasified Vater x n# " 4, y,p, I , -e'$.;., ' w
- 96-18 RDFht Drain . %+ -a 4"
'Ae Q N# 86-iS7C Co ~ Reheat Co'11 M m'2'# "' " # .M w-b 4."'W ~ 86-16%tal1It1-lotation Fins #*-
,. x l *'T '- we
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- 86-200 Anti-Rotation Fins for x
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W.86-251 lace.CCO Step Check x s
~
. ~.w 86-258 Replace Voltage Reg ITA
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. As - Jend ITB Filter j x
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p# " . . ' 86-163kepY PSA N15aT " l ' " * % .. r ' N *'
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- 5. l l 86 'J7 Replace Rectifier Flovseter
~~
x l
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86-401 FI-RC2A6 Instr Ckt Design x l
l O. ' 86-403 Instl CF-30 & 31 x Anti-Rtn Dvc
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86"-410* Inst 1 Mech Ses1Notrsee . orf N
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n". 87-004 Repl Ters Blk w/Raychea x " " Sp1
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87-021 Rev Limitorque Let SV x ~ ~ 3%, Ituabers '
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- x 3 M " .~ g g ,p M %, +
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M e yq y dh 87-1019 Add SFAS Rad Mon x 1W 4 ' y,g;:<%s condectors . ce
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aw y , , ~ e- W* 47-1021 SOR Replat Due to'Diaphraa. ' x Mt1 , , . . . N% ;. ~ ~vm w je7-1025'Chng Screws TB-4 in ARTS Cab % . x*
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.. ~47-1033 Rep 1 MDT-20 Position 5 Board 3,
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- 9. - '
m #87-1041 x
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- N 7-1098 Instl Et Trace CR /ES -
x N.. . ' 4, 87-1100 Repl Obsolete Baily Instr
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%,0 87-1101 Remove BTU Limits From ICS .. x
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SCBDUt2 IMPACT
,M_00, DESGIFTION _ NOW NINIIME MAJOR
. - -e e 7. -u M.1139,4eveh-Talfe'ItMNt1 Change' 4-M %-TM (kk d-9. .h.ek f >. . - w tes g.. h O' ~ -.
I'"' ' # 87-1141 cire BreT E Fall Prot'Irip x
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87-1142 Gen Trip for Stator Grnd Flt x y aw 'g. men " % yek 87-118 g Cooled Osad FFG Conn J* W . , x w~ P l
-%'s
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4
.- l TURBINE AND TURBINE CENERATOR ACTIVITIES
.h m P .uAV w ., ~>-- t% % he.
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<.m 1. Nm mum. .
. awe A. L P "A" INSPECTION ppw. . ; .w '
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,,, DIAPRRAN REPAIR e 4.or~ s e s.
- vggBIMONICe+-' w 4~p -
y ' INSTALL VARNING THERh0COUPlas#.
~. BLAST CLEAN ROTOR AND DIAPERAMS
+. ,
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,4 .. 'TIEVIREINdALLATION " " ' W. h ~' * * # #4#
1' A.r+- VRE11. SONICS .1 ,
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BLAST CLEAN ROTOR AND DIAPERANS'
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A n- NOTE: T'RE RESULTS OF THE TORSIONAL TEST VIE DETERNIH VRICE, IP ANY, L F TIRBINE WILL BE -
+ . .
DTSASSEMBLED. DEPEBWIM'ON TEE RESULTS . EITHER L F "A", or L P "B", OR L P "A" AND
- o. . .
"B",
~~ M .TIEVIRE ORINSTAMATIONS.
NEITIER VILL REQUIRE DISASSEMBLY '
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C. BEARING INSPECTION a%.
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,* ,, ' 'INSPBCTION WILL BE PERP Q jag 8D ON g- ' 90RK'90098 DIaAASERARI.T w * +
.* .; I? TURBINE . REARING 1 AM,b !
.,j, PMA" MSDS BREARIME-3 AND 4 1%*
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- L'ta!5".TURBINt
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" B.PERPORN.C9'?ER DUSTING REVIND OF FIELD
, C. REPLACE FI D RETAINING RING VITH INFROVED MATERIAL . . . , . O'!g. D. REPLACE GENERATOR MAIN LEADS E. CLEAN, INSPECT, AND VARNISH GENERATOR P. CLEAN AND INSPECT ALTERREI g ., ,~ , a-G. REPAIR ALTERREI COLLECTOR RINGS ",
-wu . .
- - 3 3-
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, , _ . _.._-.m . . _ . _ , _ . _ . - . _ _ ~ _ _. ~ . . , , , . _ , , . . . _ . . . , _ . _ - _ . _ - _ . . _ _ , _ _ _ . _ _
. =
4 l
- 3. ELECTRO BYDRAULIC CONTROL A. THROUGH FLUSH OF SYSTEM B. REBUILDING ONE EHC PUMP C. NORMAL P.M.'S
- 4. TURBINE VALVES
. m. <- .,_ m _
. . , _ +~ - . - . . -
A. INSPECT TWO MAIN STOP VALVES B. INSPECT TVO CONTROL VALVES C. INSPECT TWO COMBINED INTERMEDIATE VALVES D. INSPECT TWO REHEAT SAFETY VALVES CHECK SET POINT ON ALL VALVES DURING START UP
- 5. MOISTURE SEPARATOR REHEATER I A. OPEN AND INSPECT FIRST AND SECOND STAGE TUBE BUNDLE AREA l B. PARTIAL IMPLEMENTATION OF FCR 81-223/RFM l 87-1164, VHICH CHANGES MANVAYS TO AN EXTERNAL SOLT ON DESIGN
( *
~ ~ONLY FOUR OF BIGrf MANVAYS ARE SCHEDULED
'FOR EACH MSR. TEE FOUR SELECTED VILL SUPPORT THE ABOVE INSPECTIONS.
- 6. IMPLEMENTATION OF PRIORITY TIL'S AND ECN'S l
- 7. MAINFEED PUMP TURBINES l l
A. MAIN 1?EED PUMP TURBINE NUMBER 1 AND iRIMBER 2 I
- DISASSEMBLE, INSPECT AND EEASSEMBLE,.
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i l l STATUS: VORK SCOPR'S OF THE "A" AND "B" L P TURBINES IS C0ffrINGENT ON THE TORSIONAL TEST RESULTS. PARTIAL ARC MODIFICATION VILL BE PERFORMED ON THE HP TURBINE Biff NO VORK VILL BE DONE ON THE N0ZZLE BI4CK.m THE GENERATOR ", VORK VILL BE PERFORMED AT GENERAL ELECTRIC. BOTH MAIN
.u _.,, FEED PUMPS TURBINES. VILL BB VORKED DURING THE,0UTAGE AND ,
RALF THE MAIN STRAM VALVES VILL BE INSPECTED. GE VILL BE RESPONSIBLE FOR THE SCORE OF THIS VORK. MSR MANVAT VORK SCOPE HAS BEEN REDUCED TO FOUR MANVAYS PER MSR UNLETS TIME IS AVAILABLE TO DO ALL EIGHT. THIS VORK VILL BE PERFORMED BY TOLEDO EDISON. CONCERNS:
- 1. TURBINE - GENERATOR VORK VILL BE CRITICAL PATH FOR THE 5TH REFUELING OUTAGE AS IT IS ESTIMATED TO TAKE 10-12 VEEKS.
- 2. QA CONCERNS ASSOCIATED VITH GE MAINTENANCE PROCEDURES TO ENSURE DOCUMENTATION OF VORK PERFORMED IS IN COMPLIANCE VITH DAVIS-BESSE
. ADMINISTRATIVE: PROCEDURES.. 4 ,
- 3. FINALIZATION OF THE' C0fffRACT VITH GENERAL ELECTRIC i ConPORATION.
> l
- 4. ,VORK SCHEDULE FROM GENERAL E!2CTRIC TO COORDINATE i VITH DAVIS-BESSE'S VORK PLAMING SCHEDULE (P-2). l
- 5. ESTABLISHING AND COORDINATING APPROVED WORK AREA FOR CONTAMINATED TURBINE, Ale MFFT COMPONENTS.
- 6. ENSURE RAIL SITES ARE AT THE MAINTENANCE LEVEL REQUIRED FOR TRANSPORT OF TR MAIN GENERATOR 1
, OFF-SITE TO, GENERAL. ELECTRIC AND RETURNED TO % _
D&YIS-BESSE. ,. . u
i . ISI ACTIVITIES SCOPE: Approximately 500 ISI (In Service Inspection) Activities are planned for the 5th refueling outage. The activities by area are as follows:
- a. _ Containment. , ..,% .
- 1. Eddy current testing of tubes in both OTSG's.
- 2. Ultrasonic testing of shell and norsle velds in both OTSG's and the pressurizer, the flange /shell veld in the RPV (Reactor Pressure Vessel) and various piping velds.
- 3. PT/MT of various piping velds.
- 4. MT/UT of RPV head bolting. "
- 5. Pressure testing of the RCS and other systems.
- 6. Visual inspectica of various component supports and valve internals.
- 7. UT core barrel bolts.
- 8. ARIS (UT) Reactor Vessel (Decision Pending).
- b. Auxiliary Building
~ , .n , M'* . n .~ ~
- n. ..
- 1. MT/PT~of various piping and support velds.
- 2.
Visual inspection of various' component supports and component bolting. Pressure testing of various s/ stems.
~
3.
- . - . w m , ,. . ,
- c. B.O.P. (Balance of Plin,t) n, ,, ,,
, 1. UT thickness readings of various piping. ,_
- 2. Eddy current testing of condenser tubes and feedvater heaters..
- 3. Hydrotest APPT steam piping.
. . ..~ m ~~-m.<,, -
-u~
34:
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STATUS: Detailed P/2 information has been developed and
- _ , _ inputting is underway. Budgetary quotations have been.
received from B & V with final' task description and ' " , detailed cost data to be provided by the end of ,_ s September. "4*3' ' Performance Engineering has reduced the number of Peedvater Heater Eddy current exams fros.eight to two," (H P heaters E5-1~and E 5-2). Core barrel bolt inspection has been established at Upper Core Barrel and Accessable Lover' Core Barrel bolting only. A meeting to discuss ISI craft support and work order requirements vlll be held before the end of J i
- .- . - _ _ _ ., _m. __ . , _ . , _ _ . . . _ - _ _ . _ . _ _ _ _ _ . . . _ _ . . _ _ , _ _ _ . _ _ . _ _ _ . . _ . . , _ . , _ _ . _ _ . . . , , _ _ . - - .-.-._,,--..-m
?
l September. Systes Engineering has generated their ! recommendations regarding the extent of OTSC Eddy l Current exams and bubble testing. These reconsendations are being forwarded to the Flaat Manager. CONCEMS: A management decision regarding performance of the ARIS inspection is required. This.will facilitate.the-planning of containunt activities. A manag'eent e
+m- *' decision,regarditg.the performance of OTSC bubble- ,
testing vill also be esquired~for the same reason. Performance Engineering must provide the pressure / hydro testing to be done to allow planning of these activities with modifications, surveillance testing and post-modification testing. Systems Engineering has indicated the potential for OTSG secondary side bubble test inspections. This must be identified without delay for integration into Containment planning. FCR 87-119 (Tech. Spec. change for Eddy Current Inspection) must be issued prior to refueling to ! implement the tube inspection scheme proposed by Engineering.
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~
I
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CORRECTIVE MAINTENANCE i SCOPE: s Presently 570 MV0's an increase of 113 are outage 1 related. The present trend is approximately 10 - 15 nov
- x:
- MV0's generated per week that require an outage.
' . a ,m . -
I STATUS: Current MVO numbers indicate a need for increasing our "banked" outage MV0's in order to support an unplanned outage and also in support of the 5th refueling outage ; plan. A large number of MV0's are on hold for shop , review or for engineering an'd'are being addressed as i potential problem areas.
- Of the current 457 MV0's that are outage rel.ated 422 are classified as Outage corrective Hvo's and a further breakdown of these indicates the'ToTIoving status: "
Material Nee p. 3-2 73 ,t Vork Packageded . Preparation - 118 Shop; Review /Peedback+' - 56 "* ~ Bold for Engineering - 31 Avaiting Outage' ,
- 144 422 Total - -- '~
- . n-a The remaining 148 fall into one of three categories:
MVO generated to support N00's MVO generated to support PM's MVO generated to answer PCAQ's
, _. ...... -4 _& ~ + + ~ ~
' . - - 2,,.
Most of"the above'148 MV0's 'areTenerated to support modifications with a considerable, effort remaining in PM support which should be addressed as a potential problea ' i area at this time. ~. -
- c. ,, . -, ,
kg -'
*e 9
MANPOWER PROJECTIONS 1 ATTACIDeff I is a compilation of all the manpower requirements identified to date by type and work effort. Outstanding concerns ares
, . - s. , . : ,. w -
- 1. 'None of the Refueling PM's or ST's have been added into the breakdown. .
- 2. Only 96 of the 116 MODS identified have had resource requirements entered into Mod Schedule.
ATTACIDeft II is s' comparison of the total manpower limit for effective utilization. The increase in manpower required is l' primarily the result of re-evaluating the workscope of FCRS/ MODS scheduled. Outstanding concerns are:
- 1. Major efforts such as refueling, turbine overhaul, ,
ISI, LLRT or Systes Engineering special requests I have been fully evaluated as to the extent for additional manpower. r c - (. " " '
- 2. 'Although approximately 25% of the scheduled work can l
4 be worked as pre-outage work, delay ~to Engineering work package issuance and untimely material delivery have the potential to cause this work to be implemented during the eutage.vindow.
- 3. A significanT number of 05 FCRS are experiencing Implementation impairments. The ramifications of l these vill cause an overflow of non-outage work into i the pre-outage work. At this point in time, no I difforentiation has been made in priority for 05 and 05R. Accordingly, SR vork may be impacted by work
,_ .which could be rescheduled until after the Refueling Outage.
w, . O '.N h l 42-
... . - - . . . . .s . . e_ -> - + n z;. .-- G ~ ~ l .. .t .
FIFTH REFUELING OtJTAGE MANPOVER ESTIMATE I BASED ON 96 OLTT OF 116 MODS l I TED DBHMS "" PM 'ST MODSCHED TOTAL MEN l ELEC s 5.0 2.5 2.3 6.0 16.7 ; MECH 23.5 1.3 0.5 26.6 51.9 ' IC 3.6 M 12.5 13.8 30.9 SUBTOTAL 32.1 4.8 15.3 47.3 - 99.5 1 CONTRACT DBHMS PM ST MODSCHED TOTAL MEN
^
ELEC -- 0 0 142.6 142.6 l MECH -- 0 0 45.3 45.3 l OTHER 7.6 0 0 17.5 - _ 25.1' SUBTOTAL' 7.6 0 0 205.4 213.0' SUPPORT DBMMS PM ST MODSCHED TOTAL MEN OC . 2.9 0.4 1.2 18.5 23;0 RAD CON " 42.2 J O 0.8 14.0 57.3 SUB TOTAL 45.1 0.7 2.0 32.5 80.3 mm . ', er '6. %) 9 43 DBHMS PM ST MODSCHED TOTAL'NEN' TED 32.1 4.8 15.3 47.2 99'.'5 ~ C0!frRACT 7.6 0.0 0.0 205.4 213.0 SUPPORT 45.1 OJ 2.9 32.4 '80.3 TOTAL 84.8 5.5 17.3 285.2 392.8
l l \ l REFUELING OUTAGE (5R) AND OPERATING CYCLE (8) SCHEDULE saan we m.y Jun an. aus anP oct mov sec Jass rue esas we mar Jun an. aue ser ocT mov asc Jam res anam I I STM CYCLE REFUEUBIG OUTAGE MARCH 11. 1988 TO SEPTEWlER 12. 1988 100AAAAL OPERATB001 SEPTEMBER 13. 1988 TO JAtJUARY 17 1990 ( not, yet, approved) T h W m
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l 1 Deferred /Daletion/EMDD review for rescheduling or crediting. Approximately 150 PM's still require material to be identified by System Engineering and BOM's submitted. The number of manhours estimated for all preventative maintenance from the time frame of December 1, 1987 to May 31, 1988 is approximately 50,000 manhours. Procedure NEP 074 training is continuing with completion delayed to September 15, 1987. Modification Activities: The current forecast dates remain unchanged since the last issue. Impact to the SR Outage is addressed in the Modification Activity section of this report. Engineered material must be identified as soon as practical in order to obtain needed vendor drawings, manuals and hardware. Dravings and vendor manuals vill provide the needed information for new instrumentation data packages, test procedure developmen: and maintenance procedure revision. NCR & PCAQ Activities: 4 The NCR and PCA0's, as they relate to the Outage Licensing Commitments, deal mainly with the hanger review program. These two document types fall into various categories, and are as follows: NCRs that are draving change only. - This group is the majority of the existing NCRs. NCRs and PCAQs that are in Engineering for disposition of which Operating Cycle work may result. PCAQs the hanger valkdown program generates that result in additional Operating Cycle work. Identified work items that fall both in the Operating Cycle and the Outage. The inspection of information gathering area that encompasses A.I.R.'s, (Additional Information Requests)in Containment and new valkdowns in the innulus and Control Room,as these can only be performed during an outage. Engineering has issued a vork-off schedule for both the valkdovns and dispositions. Except for the Annulus, Contain6ent and Control Room work, all valkdowns and dispositions vill be completed by the end of September and November, 1987 respectively. This schedule vill allov for completion of all Non-Outage Hanger vork prior to the start of the SR Outage. Note: The above has been scheduled in support of the February 1988 outage start date. Concerns: There are two major areas of concern within the outage itself, those are the scaffolding requirements in the Annulus and Control Room to. perform the inspections. The Annulus vill need four scaf folds two hundred and thirty foot to be built and lef t to support any resultant vork from Engineering's dispositions and hanger inspections. The Control Room vill require scaffolding over the Control Roon operating consoles and stand up panels. This vill be critical and vill require a great deal of operations coordination support. LCTS Activities: The finalization /quantification of SR LCTS commitments is complete and preparations are in progress for the presentation for NRC approval in late September. The list has 260 5R. commitments of which 131 are actual NRC commitments. 129 of these items are planned for completion before the end of the SR outage. Identification of SR LCTS required FCR's/MV0's is forecast to complete by September 15, 1987. Corrective Maintenance Activities: Backlog SR MVO and vork request review and evaluation for 3R vork continue towards an October 1, 1987 completion date. Material is being ordered in conjunction with the review and preparation of the work packages. All known vork packages required to support 3R Outage Activities vill be complete by October 15, 1987 as scheduled. The completion date for the revision of the DBMHS MVO format still remains December 1, 1987 to allov for computer software development. This late implementation of the new MVO is not 4 expected to impact vork package preparation as it continues into and through the SR outage. ' Test Procedure Activities: Test review of SR FCR/ MOD's continues as the detailed design is issued. The development of the test procedures (TP's) is progressing also. Performance Engineering is continuing to hire additional test personnel to assist in writing and implementation of the TP's.
- SR Schedule Development:
- Emphasis since last report issue has been placed on the manual development of an overage outage "plan". This "plan" reflects all proposed SR FCR/ MOD's, in addition to major corrective, PM and testing activities. In summary, the plan shows the critical path being shared between the T/G vork and several FCR/ MOD activities.
Vhen the preoutage vork, FCR/ MOD detail design completion, and material delivery dates vere incorporated into the plan, it became evident that some FCR/ MOD's cannot be worked without extending the INTRODUCTION The current schedule calls for Davis-Besse to conduct a reactor refueling during the first quarter of 1988. In addition to this major activity ve vill also accomplish a number of other work items requiring the same attention to detail. In order to fully appreciate the significance of each vork item within a refueling framework, the scope of each vork iten vill be identified in future POD agendas. The following objectives have been established for the Fifth 1 Refueling Outage: Total defueling/ refueling Completing all licensing required modifications Completing a large number of plant improvement modifications Completing a major inspection and overhaul of the turbine generator Completing a scheduled In Service Inspection (ISI) Completing all outage related maintenance work orders (KVO) , Performing a required Integrated Leak Rate Test (ILRT) A review of the above objectives and an understanding of the scope of work related to each item describes a "full plate" for the current scheduled outage time frame. A close partnership vill be required between all groups at Davis-Besse associated with the 5th Refueling Outage in order to achieve our stated objectives. The key to this refueling outage, performed on time and within budget, vill be the proper and thorough Planning, coordinati'n o and timely reporting of progress and problem identification prior to and during the outage.
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