ML20071P904

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Requests Meeting to Discuss Integrated Mod Schedule for Unit 2,mod Deferrals Proposed & Justifications Provided. Scheduled Outages,Coupled W/Normal Forced Outage Rate,Could Result in Lack of Sufficient Operating Reserves
ML20071P904
Person / Time
Site: Sequoyah  Tennessee Valley Authority icon.png
Issue date: 06/02/1983
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Adensam E
Office of Nuclear Reactor Regulation
References
NUDOCS 8306080212
Download: ML20071P904 (36)
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.. TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ol 400 Chestnut Street Tower II June 2, 1983 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.~ 20555

Dear Ms.'. Adensas:

In the Matter of ) Docket No. 50-327 Tennessee Valley Authority ) 328 Please refer to my April 14, 1983 letter to you concerning our integrated modification' concept for the Sequoyah Nuclear Plant unit 2. The letter provided informabion on the unit 2 integrated modification schedule which included the deferral of modifications associated with the completion of several unit 2 operating license conditions.

During a telecon held on April 26, 1983 concerning the proposed unit 2 modification schedule, y2u requested additional information which is necessary to provide adwquate justification for the license condition items for which we plan to defer modifications. Enclosed is additional information.

Enclosure 1 shows the net effect on the length of the unit 2, cycle 1 and the unit 1, cycle 2 outages and the financial impact because of lost

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generation if TVA is required to complete all of the operating conditions before unit 2 is allmd to restart. Enclosure 2 discusses past efforts to complete each requeded deferral item and what our completion problems have been. Enclosure 3A lists the majority of the NRC-related modifications identified since the unit 1 operating license issuance. Enclosure 3B shows the man-hours expended to date, the percent of completion, and the completion or projected completion date for each modification. The information _in Enclosure 3B has been updated through May 9,1983 Some items are currently unrcheduled because of incomplete scope. To date, TVA has expended approximately 1,133,000 man-hours with an estimated 4,120,000 man-hours remaining before all of the items listed in Enclosure 3 are completed. Enclosure 4 shows_the current TVA projections to complete the remaining modifications scheduled in Enclosure 3 through the end of the unit 2, cycle 2 outage. Enclosure 5 shows -the current TVA integrated schedule for Sequoyah Nuclear Plant connitments. It should be noted that all the schedule dates assume that the requested commitment deferrals are approved by NRC; otherwise, all of the dates will be affected.

8306080212'830602 "

PDR ADOCK 05000327 An Equal Opportunity Employer F

- U.S. Nuclear Regulatory Commission June 2, 1983 It is evident from looking at TVA's previous comunitments on the NUREG 0737 modifications that problems have occurred on major modification scheduling.

However, we prepared these schedules with the best design and material delivery information available at the time. We have been unable to meet these schedules because many of the designs and materials needed for those schedules were not available on the originally projected dates. During the development of our integrated outage schedule, we identified items for which material and design would be available. From this listing, we identified and prioritized those items with the most safety benefit.

Through this process, the items listed in Enclosure 2 were identified for deferral. Material or design difficulties affect three items and the fourth item will have no safety benefit in the near future.

We would like the opportunity to meet with your staff at your earliest convenience to discuss our integrated modification schedule for unit 2, the modification deferrals proposed, and the justifications provided. We believe that we will be able to respond to any unanswered questions at that time.

If there are any further questions preceding this meeting, please call R. H. Shell at FTS 858-2676.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills,11anager Nuclear Licensing Sworn to jand subs r bed before me thisjn.# day of ht'983 IAd 1 @1/

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Enclosures cc: U.S. Nuclear Regulatory Consnission (Enclosures)

Region II Attn: Mr. James P. O'Reilly Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

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ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT SCHEDILE IMPACT FROM COMPLETING EXISTING NRC C00MITIENTS BY THE END OF THE UNIT 2, CYCLE 1 AND UNIT 1. CYCLE 2 OITIAGES The' purpose of this enclosure is to show how TVA's outage schedules are impacted-if all licensed NRC commitments for unit 2 are required to be completed by the end of the unit 2, cycle 1 outage and all licensed NRC commitments for unit 1 are required to be complete by the end of the unit 1, cycle 2 outage. Also shown is the effect on the subsequent cycle for each unit as well as the estimated cost in lost generation.

There are several restrictions which are imposed during an outage for the purpose of maintaining a high degree of quality and safety. Each trades-and labor employee is limited to working eight hours overtime per week and no more than twelve workdays in fourteen calendar days. All critical work is scheduled on three eight-hour shifts whenever possible. Also, a maximum trades and labor personnel limit of 750 has been established to perform modifications and major maintenance during the outage. The information below has been derived based on these restrictions.

Unit 2 is currently scheduled to shut down August 5, 1983, for a 91-day outage. Seventy-four days will be available for work on modifications and the remaining 17 days will be taken up ';y shutdown, testing, and startup.

In addition, we have experienced a historical outage overrun of 25 percent. Thus, if overrun is included, the estimated outage duration would be 114 days.

There are 25,900 man-days (350 men) of modification work and 24,050 man-days (325 men) of maintenance work currently scheduled during the unit 2, cycle 1 outage. Out of the 25,900 man-days presently scheduled for modification work, 2,508 man-days of work have been directed towards completing the Postaccident Saspling Facility (PASF) and the Technical Support Center (TSC) modifications. With TVA's current manpower restriction of 750 trades and labor personnel onsite during an outage, this leaves 75 men available for emergent work. Thus, a total of 49,950 man-days of work, excluding emergent work, are presently scheduled for the unit 2, cycle 1 outage.

An additional 20,580 man-days of unit 2, cycle 1 modification work would be required if the PASP, TSC, vessel level, and high-range monitoring modifications were required to be completed by the end of the outage. This would bring the total to 46,480 man-days of modification work. By shifting 75 men from maintenance' work to modification work (425 men total), the 46,480 man-days of work would take 109 days to complete. An additional 8 days would be required because of the logistical impact of increased QA work and "C" zone work. Also, 2 days would be required for shutdown to mode 5,10 days for systems training and secondary water cleanup before mode 4,-and 8 days to go from mode 4 to generator sychronization. Thus, the total estimated outage length would be 137 days. By including a historical overrun of 25 percent, the estimated duration would be increased

.by 35 days to a totsi of 172 days. This amounts to a unit 2, cycle 1

' outage extension of 58 days (including overruns) of which 28 days are overlapping with the unit 1, cycle 2 outage.

The unit 1, cycle 2 outage is currently scheduled to begin on December 27, 1983, and is estimated to be 79 days in length. Including a historical estimated outage overrun of 25 percant, the estimated unit 1, cycle 2 outage length would be 99 days.

There are 27,600 man-days (400 men) of modification work and 18,500 man-days (275 men) of maintenance work currently scheduled during the unit 1, cycle 2 outage. This leaves 75 men available for emergent work.

The current schedule allows 15,300 man-deys of nonoutage modification work to be completed between the unit 2, cycle 1 and the unit 1, cycle 2 outages. If the unit 2, cycle 1 outage extends to 172 days, this 15,300 man-days of work will have to be completed during the unit 1, cycle 2 outage. Thus, there will be a total of 42,900 man-days of modification work to be performed during this outage. By shifting 25 men from maintenance work to modification work (425 men total), the 42,900 days of work would take 101 days to complete. In addition, 6 days would be required because of the logistical impact of increased QA work and "C" zone work. Also, 2 days would be required for shutdown to mode 5, 5 days required for systems training and secondary water cleanup before mode 4, and 6 days required to go from mode 4 to generator eychronization. Thus, the total estimated outage length, excluding outage overlap and overrun considerations, would be 120 days.

Twenty out of the 28 days of outage overlap will directly impset the unit 1, cycle 2 outage length day-for-day because of all available manpower being required to support the unit 2, cycle 1 outage. The other 8 cays I which are required for unit 2 startup will not impact the unit 1, cycle 2 outage length. This 20-day extension, coupled with a 25 percent historical l_ overrun (30 days), results in a total estimated outage duration for the

! unit 1, cycle 2 outage of 170 days. This amounts to a total extension of

, 71 days (including overrun) for the unit 1, cycle 2 outage.

I The graph included in this attachment depicts the manpower requirements and outage durations for the existing outage schedules and the forced schedules (complete all commitments as licensed) for the next two outages on both units.

Power replacement cost for TVA's nuclear plants varies between $200,000 and

$280,000 per day depending on the time of year the unit is shut down and the amount of system generation that is out of service. The power

replacement cost for the 58-day extension on the unit 2, cycle 1 outage is approximately $15,340,000. The power replacement cost for the 71-day extension on the unit 1, cycle 2 outage is $17,750,000. Because of less work having to be performed during the unit 2, cycle 2 outage, the duration would be expected to decrease from 79 days to 68 days. This 11-day decrease in outage duration would equate to a cost savings of $2,200,000.

Thus, the total lost generation cost to TVA would be $30,890,000.

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The overlapping unit outages at Sequoyah as described above would coincide with a probable generator rewind outage on TVA's Paradise Steam Plant unit 3 and a scheduled modification outage on TVA's Browns Ferry Nuclear Plant unit 3 This would result in a total of 4,379 MW being scheduled out of service during the peak period in the winter of 1983 through 1984.

These scheduled outages, if required, coupled with a normal forced outage rate on other units could result in the lack of sufficient operating reserve to meet system demands.

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ENCLOSURE 2 DEFERRED LICENSE CODMITPENTS ITEMS TVA has previously prepared tentative schedules to meet the operating license commitment dates for both units. The following four items will not

> _ meet the unit 2 operating license commitment dates because of the following .,

problems.

11. Reactor Vessel Level Indicating System - 2.C.16.m.2 The reactor vessel level system has been scheduled for installation 1

during the second refueling outage because of its severe impact on work activities and because the system cannot be operational until emergency procedures utilizing the level system are developed, approved by NRC, and subsequent operator training completed. Sequoyah Nuclear Plant procedure guidelines are beinr leveloped as a generic effort by the Westinghouse Electric Corpe , ion Owners' Group. Based on the present Owners' Group schedule, t; e procedures cannot be in place and operator i training' completed before the fall of 1985. The level system, if

' installed durir.g this outage, could not be used until approximately two years after installation. Westinghouse has indicated that additional analyses will be necessary for plants utilizing ice condensers and/or upper head injection. The magnitude of this work and the schedule for completion have yet to be determined.

- In addition, with present manpower limits, this modification cannot be completed as presently required without.significantly affecting the unit 2, cycle 1 outage length. Because of the large amount of containment work which is already scheduled to be performed during the j

unit 2 outage, deferral of this modification is required.

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i. 2. Postaccident Sampling - 2.C.16.g

' Material delivery for this modification is estimated to be complete by the fall of 1983 Any vendor delivery problems could delay this date by several months. The remaining nonoutage portion of this l

modification will take more than 25 weeks to complete. Because of this l

remaining nonoutage work and the current scheluled start for the unit

! 2, cycle 1 refueling outage, TVA cannot complete this modification without significantly affecting the unit 2, cycle 1 outage length, until the end of the unit 2, cycle 2 outage.

In the interim, as indicated in our response to NUREG 0578 and NUREG 0737, procedures have been established to evaluate the primary coolant system activity depending on the accessibility of the sampling L

stations for particular degraded conditions. TVA's response to NUREG 0578 contained a copy of Sequoyah Nuclear Plant Technical Instruction 66, Postaccident Sampling and Analysis Methods.

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3. Technical Support Center - 2.C.16.o.1 In the response to NUREG 0694, TVA committed to installing tbc

. permanent Technical Support Center (TSC) by June 30, 1983 Subsequent license conditions were included in the unit 2 operating license to require installation by the first refueling outage or the first scheduled five-week outage after May 1,1982. Since these license conditions were established, equipment deliveries and design work have not kept pace with the expected schedule and will not be available to allow completion during the first refueling.

J The software program for the TSC computer system was supplied by Westinghouse. Westinghouse's original delivery date for the TSC computer software 'was January 1,1981. Westinghouse's delivery did'nat

.I meet the originally scheduled date. Portions of the software were l delivered over two years late to TVA. Modifications to this cortware package by TVA are expected to be complete by the summer of 1984. The nonoutage portion of this modification will take 29 weeks to install.

As currently scheduled, this nonoutage pertion will not be completed before the unit 2, cycle 1 outage work begins. The magnitude of this

, work will not allow completion of the TSC until the end of the unit 2, cycle 2 outage unless the unit 2, cycle 1 outage length is significantly increased.

The TSC, which is located adjacent to the main control room, is being used at Sequoyah. The TSC meets the same habitability requirements as l the main control room. The TSC communicationn include PAI telephones and Bell telephones. Reference materials, including the Radiological Emergency Plan (REP), implementing procedures, plant drawings, Final Safety Analysis Report (FSAR), and selected plant procedures are

! present. Therefore the TSC is presently operational with the exception l

of the appropriate data systems.

4. High Radiation and Iodine Monitors - 2.C.16.1.2a NUREG 0737 gave little guidance on the instrumentation specifications required to meet NUREG 0737, II.F.1. Because of the lack of guidance, TVA creat'ed their own specifications for the required radiat' ion

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monitors. After several months of trying to procure radiation monitors, TVA discovered that they were not available using,TVA's current procurement specifications. The time it took for TVA to find l an approved vendor utilizing the specifications delayed the purchase of-

the radiation monitors until September 1982. This resulted in delaying j completion of the design until August 1983 The present schedule for completion of this modification is before

'startup after the unit 2, cycle 2 refueling outage.

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A te 3-By the.end of the unit 2, cycle 1 outage, Sequoyah will have installed

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high-range noble gas effluent monitors as follows: -

At Monitors will be placed on the shield building vent and the

, condenser vacuum pump othaust.

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, 3. Each nonitor will consist of two General Atomic Company monitors as

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1. Model. RD-1 with a range of 10-1 to 10+4MR/hr

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2. Mcdel"RD-23 with a range of 103 to 10 7MR/hr Note: The model RD-1 and RD-23 monitors each utilize an ionization chamber for the detector.

_- C. The instrument readouts with continuous display and recording will be located in the main control room.

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D. The source of power for monitors will be preferred power (vital instrument bus).

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ENCLOSURE 3A NRC-RELATED MODIFICATIONS /

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'ECN DCR DESCRIPTION -

DOCUMENT 5207 Change ductwork on ABGTS for 1/4-inch IE Inspection 81-36 '

negative pressure in ESF oump rooms .

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a 5050 231 Gas effluent radiation monitor , IER 327/79-48, IE (complete). Inspection 79-48, Item 3 '

5033R1 262 RHR loss of flow alarm in main control ' FSAR question 5 57 .

room (complete). g 5045 322 Reactor overpressurization instrumenta- U1-OL2.C.20, U2-OL2.C.7 tion. ,

5047 351 Under/over voltage alarms on 6.9kV U1-OL2.C.18.c shutdown boards. -

5588 388 Modify RP-30 ratemeters (completed on U1-OL2.C.18.a, TACF 82-220). U2-OL2.C.11.a

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5384 575 Penetration X-54 and X-118 (complete). Browns Ferry LER 50-259/79-38, 10 CFR 50 Appendix J 5330 593 Revise door locking systcm. Physical Security Plan, 5426 Appendix E 4.0 5321 595 Intrusion detection aids - PERIM-Alert IE Inspection 80-27, II. Sectiop 02 y 5249 654 Provide automatic backup system for LER 67138 /

blowdown valve actuation (complete). J-l 5253 675 Correct errors in seismic supports in LER 80173

! CCW system because of inaccurate valve weights (complete). t , ;f 689 Reactor water level indicator. U 0 2 C 23 5119 706 Install radiation monitor cable in LER 82068 < ' '

s conduit. ,

l 5555 715 79-14 alternate analysis - IE Bulletin 79-14 /

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I inspection unit 1 piping hangers. <

5277 715 Review deviations from as-built IC Bulletin'79-14 s drawings for piping hangers. 1.ERs 81023, 81010 i

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ECN DCR DESCRIPTION DOCIRENT

- 5286 '716 Add grills to ventilation ducts. IE Inspection 81-18

.-5312' 721 Install card reader system on door 10 CFR 50.54(f)

A-183.

I* 5118) '722' Remove STATIC Corp. Inverters 2-I, LER 80166

-III, and -IV and replace with solid state controls (complete).

t 5298 737 Reroute ERCW train B fire cables to 10 CFR 50.48 obtain 20 ft. separation (complete).

5297 740 Upgrade spent fuel pit gates (complete). Reg. Guide 1.13, 5725 LER 80045 5712 741 Evacuation alarm system audibility. IE Inspection 82-11 8.C 5235R1 741- Revise piping to HVAC equipment for Preoperational Test electrical board rooms and main Deficiencies 176, 320, control room A/C. 329, 367.

' -i 5196' 751 Wide-range containment pressure TMILL-2.1.10, NUREG 0578 monitors. U1-OL2.C.23.d, NUREG 0737 412776-p 5197 752 Reactor vessel ventilation system THILL-2.1.13, NUREG 0578 (unit 1 partial complete). U1-OL2.C.23.e, NUREG 0737

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, 5352 753 Add additional phone lines for TSCs U2-OL2C.16.r.3

(complete). NUREG 0737 Letter 82-33 s

5001 771 Coat surfaces with Flamemastic 77 Revision 4 Fire 2911 (complete). Protection Submittal

'5109 774 Control room openings in walls. IE Inspection 80-20 i ' Section 01 520!i 779 Postaccident Sampling Facility U1-OL2.C.23.f, SER II.B.3 2780.' (units 1 and 2 partially complete).

780 High-range effluent monitors TMILL-2.1.8.B, NUREG 0578 5193 U1-OL2.C.23.f, NUREG 0737 2773 5194- 781 Iodine radiation monitors. TMILL-2.1.8.B, NUREG 0578 U1-OL2.C.23.d, NUREG 0737

/ 5770 781 Iodine radiation monitors. TMILL2.1.8.B, NUREG 0578 U1-OL2.C.23.d, NUREG 0737 5195 782 Containment radiation monitors (unit 1 TMILL-2.1.8.B, NUREG 0578 complete). U1-OL2.C.23.d, NUREG 0737 2775 l

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!l s Erg . ]2f2 - DESCRIPTION DOCUMENT 5110 785 Interim H2 mitigation system (complete). U1-OL2.C.22.d 5311 5331 5478 5199 787 Containment isolation radiation monitor U1-OL2.C.22.f 2779 - (unit I complete). SER1 11.K.1 NPR IV.A.6.1 i

5317- 790 High-range area radiation monitors NPR-IV.A.6, 2923 (unit 1 complete). U1-OL2.C.22.f 814 Redesign vendor seismic valve brackets LER 80125 for 1-LCV-3-148 (EN DES DCR approved).

5030 820 Containment isolation valves (complete). SER 6.2.6 5591 837 W-2 switches (units 1 & 2 partially IE Bulletin 80-20 complete).

5375 852 120V vital power to NRC dedicated phone IE Bulletin 80-02 circuit (comple,te).

5023 855- Temperature monitoring system for SER1 7.8.2 some clacs IE equipment.

5364 879 Install relay 86 LOR indicating light LER 80140 and warning sign "Do not reset 86 LOR if light is on" (complete).

5334 895 Install new PRT level transmitter and LERs 80155, 80161, sense lines wff.h sealed legs 82103 (1-LT-68-312C) (complete).

L 5333 897 Change AC and DC power sources for U1-OL2.C.17, SER 15.2 level control instruments (complete).

5328 897 Reroute cables for auxiliary feedwater U1-OL2.C.17, SER 15.2 system (complete).

5451 934 Diesel generator lube oil pump NCR EEB 8111 (partially complete). IE Circular 79-12 Program to resolve ATNS problems.

936P Draft NUREG 945 New heavy duty diesel turbo chargers U1&U2-OL2.C.15.a (complete).

t 5417 946 Diesel generator air dryer (complete). U1-OL2.C.15.a, U2-OL2.C.12 4

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ECN DCR DESCRIPTION DOCUENT 5357 949 Perform evaluation / install structural LER 80180 restraints on masonry walls whose failure would jeopardize safety-related equipment. (complete).

5479 954 Replace vent flow element 0-FE-30-174 Tech Spec 3.3 3.10 and 0-FE-30-200.

5444 959 Reagent air flow to hydrogen analyzers LERs 81063 and 80182

-(completed on a TACF).

972 Balance of work for NUREG 0588. NUREG 0588 5637 972 ERCW traveling screen motor modification. NUREG 0588 5443 972 Replace flow switches FS-30-200 and 207. U1-OL2.C.12.c NUREG 0588 5420 972 Replace relays on auxiliary air NUREG 0588 compressor.

5457 972 Replace solenoid valves. NUREG 0588 5365 972 Replace various systems 30 and 32 U1-OL2.C.12.a solenoid valves. NUREG 0588 I 5606 994 Provide physical barriers to ventilation IE Inspection 81-18

. system to auxiliary and control buildings.

5467 1001 Tamper indication on key card system 10 CFR 73.55 E-Z multiplex junction boxes.

5465 1002 Install alarms with capability of being 10 CFR 73 55.C.8 monitored in CAS and SAS.

5466 1037 Alarm roof hatches to 480V board rooms 10 CFR 50.54(f) to terminate in CAS and SAS.

5731 1038 Disconnect and remove electrodyne valve NCR NEB 8112 operated heaters. SQRD 328/81-19 l

Ceiling tile in control room (complete). 10 CFR 50, Appendix A, 5408 1057 Criteria 3 5510 1058 Replace cables and conduit on air lock LER 81026 doors (complete).

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XQR AQ1 DESCRIPTION DOCUMENT 5464 1067 Electrically controlled vehicle gate and ' 10 CFR 50.54(f) public address system. 10 CFR 73.55.D.1 5411 1090 ERCW pumps thermal spot fire detectors. IE Inspection 81-14 Section 03 5522 1120 Make modifications to SQN unit 1 LER 82003 l pressuriner condensate reservoirs to ensure proper operation of pressurizer instrumentation.

5429 1123 H2 mitigation system (unit 1 partially U1-OL2.C.22.d.2 complete).

5369 1126 Revise FCV-67-152 control logic (unit 2 IE Bulletin 80-06 2873 complete).

5198 1152 Technical Support Center (unita 1 and 2 U1&U2-CL2.C.23.1 partially complete). IE Inspection 82-13 sections 03, 04, and 05 U1&U2-OL2.C.11.b 5449 1154 Degraded voltage relaying. U1-OL2.C.18.c, SER 7 3 2

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1156P Postaccident monitoring U2 OL 2.C.16.g instrumentation. SER II.B.3 5769 1165 Install isolation valves on 1-inch U2-OL2.C.9 chemical feedlines (unit 1 complete).

i 5664 1226 Provide Wells Fargo system with tamper 10 CFR 73 55e(2) i indication. Physical Security Plan Appendix E 2.0 5327 1263 Modify RWST vent to prevent freezing. FSAR question 6.52 2938 5605 1281 Replace 1/2-inch fire protection 10 CFR 50 Appendix A i sprinkler drops with 1-inch drops. Appendix R comparison 1304P Containment airlock door air leakage. LERs.82138, 82064, 81108 5536 1308 Relocate class IE electrical equipment LER 81120 5537 (reference ECN 5537 and 5478) (complete both units).

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ECN DCR DESCRIPTION DOCIMENT 5304 1326P Modifications to ensure main control NUREG 0737 room habitability. Section III.D.").4 5684 1370 RCP oil shield (complete unit 1). Response to FS'.R, U2-OL-2.C.13.c 5899 1384 Change decwing to reflect contact LER 81134 change from N.C. to N.O. 45N1699-33 Fire protection panel 0-L-631 28 relay.

5604 1389 Ionization smoke detectors in FSAR fire protection.

decon room (complete). 10-79

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5653 1399 Refueling water storage tank freeze Verbal to NRC 2/26/82 protection-(complete). LERs 82010, 81004

5709 1467 Provide redundancy of RUSCO system. 10 CFR 73 55 5685 .1474 Relay room emergency lighting (complete). Response to FSAR 5674 1482 Protection from tornado generated U2-9L2.C.5, SER 5 3 5 missiles (complete). ,

j 5410 1518 Add one fire protection sprinkler in Branch Technical Position I unit 1 Rx building annulus. 9.5-1 Paragraph C.7.A Fire Hazard Analysis 5726 1534 Feedwater sense lines freeze protection Verbal to NRC 2/26/82 (complete). LERs 80202, 81003, and l

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5700 1584 Valve room freeze protection (complete). Verbal to NRC 2/26/82 LER 82010 l 58r4 1585 Move isolation valves to accessible LER 82044 l location. Install return line to B purge air exhaust for 1 and 2 RE-90-130, 131.

I 5773 1645 .PORV changeout. NUREG 0737 Section II.B.1.2 5790 1650 To prevent dampers from vibrating closed LER 82071 during control room emergency vent (complete).

5831 1662 Review waste gas instrumentation for LER 82089 dependability.

ICH ACR DESCRIPTION DOCUMENT 1691P Separate pressurizer circuits to Appendix R Submittal maintain 20 feet separation.

1698 Revise plant protected area to reflect Physical Security Plan the power block concept. Appendix E 5.0 1713P Change logic of valves to phase B on LER 82051 containment vent isolation valves.

1730P Provide a watch tower for new protected Physical Security Plan area barrier revision. Appendix E 5.0(2) 1739L Vital access system interface with RUSCO 10 CFR 73.55 MAC 540 card access control system.

1806L Install ice condenser temperature LER 81098 recorder (unit 1 only) (complete).

5856 1808 Pressurizer safety valve loop seal NUREG 0737 drain lines. Section II.D.1 5847 1835 Modify or replace vertical type fire Special Report 83-02 dampers.

5871 1856 Relocate ERCW radiation monitors from LER 83003 above turbine-driven auxiliary feedpumps.

1877 Fuse identification. SER 6.2.0, U1-OL2.C.22.d.1 (AD 24) 1882P Install four permanent hydrogen ignitors SER 6.2.0 in the upper containment. , unit 1 cnly) U1-OL2.C.22.d.1 (AD 24) l

ENCLOSURE 3B HISTORY AND PROJECTIONS FOR NRC-RELATED MODIFICATIONS DIVISION OF ENGINEERING DESIGN ' DIVISION OF NUCLEAR POWER COMMENTS START MAN-HOURS COMP SCH MATRL START MAN-HOURS CON ECN/DCR DATE TO DATE DATE $ COMP DEL DATE DATE TO DATE DATE $ COMP (2) 5207/--- 02/05/80 103 03/21/80 100 Material 08/15/80 975 08/19/80 100 onsite 5050/231 08/22/79 1648 09/29/82 100 Material 08/02/82 34079 11/04/83 99 Commitment portion is complete.

cnsite 5033R1/262 08/22/79 425 05/14/80 100 Material 05/14/80 3328 08/29/80 100 .

onsite (1)

' 5045/322 08/22/79 471 03/26/82 100 Material 08/05/83 400 03/16/84 0 onsite 5047/351 08/22/79 1646 01/27/81 100 N/A N/A N/A N/A N/A Superceded by ECN L5449.

(3) 5588/388 01/04/82 205 06/30/83 100 Material 02/24/82 130 03/15/82 100 onsite 5384/575 01/13/81 40 06/10/81 100 Material 10/07/82 572 12/05/82 100

  • onsite 5330/593 11/19/80 106 03/31/81 100 Material 06/01/81 1' 06/10/81 100 onsite 5426/593 07/06/81 106 09/22/81 100 Material 07/01/82 167 08/01/82 100 onsite (2) 5321/595 09/24/80 241 01/09/81 100 Material 03/22/81 250 04/15/81 100

, onsite (1)

Estimated man-hours to complete the work for this ECN/DCR.

(2)

These man-hours expended are estimates because of costs being accumulated by system rather than by ECN.

(3)

Vendor drawings require approval.

?

s b'

DIVISION OF ENGINEERING DESIGN DIVISION OF NUCLEAR POWER- COMMENTS START MAN-HOURS COMP SCH MATRL START MAN. HOURS COMP ECN/DCR DATE TO DATE DATE 1 COMP DEL' DATE DATE TO DATE DATE $ COMP 5249/654 03/12/80 218 06/18/80 100 Material 01/12/81 700 10/15/81 100 onsite 5253/675 03/14/80 165 04/16/80 100 Material 05/13/80 300 06/01/80 100 onsite 5106/689 01/17/80 3286 03/31/83 100 04/83 01/20/82 10293 03/16/84 25 W RVLIS R-148; W to resolve ,

connections- b ,

2768/689 01/17/80 3286 03/31/83 100 04/83 06/08/81 1023 01/13/85 2 w RVLIS R-148; w to resolve connections 5119/706 08/11/80' 205 02/27/81 100 Material 03/15/83 471 See See ; This modificattor, will be used onsite comme..ts comments as needed for an indefinite period of. time.

5555/715 11/13/81 .4867 04/10/83 100 Material' 10/14/82. 55004 03/29/83 100 ,

onsite 5277/115 05/13/80 1730 06/30/82 100 Material 06/21/80 33109 02/09/83 100 onsite 5286/716 05/29/80 153 06/24/80 100 Material 07/25/80 250 12/01/81 100 ,

onsite -

5312/721 09/09/80 233 05/28/81 100 Material 09/22/81 281 10/09/81 100 onsite 5118/722 09/12/80 203 10/30/80 100 Material 01/23/81 30 02/18/81 100 onsi*.e 5298/737 06/30/80 260 05/04/81 100 Material 03/18/81 27789 06/26/81 100 onsite 5297/740 06/25/80 410 08/12/82 100 Material 08/02/82 3646 09/15/82 100 onsite 5725/74c 07/21/82 20 10/01/82 100 Material N/A N/A N/A N/A Documentation only.

onsite Field work was done under ECN L5297.

e-e

--- , ,- . - --- , - . . . = _ .,

l

/

4 DIVISTON OF ENGINEFRINO DESTCN ~- DTVISION OF NUrt.RAR POWER COMMENTS START MAN-HOURS COMP SCH MATRL START MAN-HOURS COMP ECN/DCR DATE TO DATE DATE-  % COMP DEL DATE DATE TO DATE DATE 5 COMP (1) 5712/741 06/30/82 286 12/30/83 20 '07/29/83 Unscheduled 12830 Unscheduled 0 (1) '

5235R1/741 03/02/80 2355 03/01/83 100 Material 12/23/80 .23006 .on hold 95 onsite 1 5196/751 01/28/80 296 05/30/83 89 11/80 12/27/83 9651 03/16/84 0 Equipment qualification to meet i

IEEE 323-1974 in order' 2776/751 01/28/80 296 11/22/82 89 11/80 04/01/83 483 11/04/83 5 Equipment qualification to meet IEEE 323-1974 in order 5197/752 01/28/80 2050 11/22/82 100 11/82 09/10/81 26578 03/16/84 86 [wleakyvalves,willreroute instrument lines.

' (1) 2777/752 01/26/80 2050 05/30/83 100 11/82 07/01/83 .12355 11/04/83 0 5352/753 11/03/80 38 04/01/81 100 Material 10/01/80 200 11/01/81 100 Completed on TACFs.

onsite 5001/771 06/26/80 8 08/08/80 100 Material 10/20/81 6643 05/03/82 100 -

onsite 2911/771 06/26/80 8 08/08/80 100 Material 10/30/81 6643 11/02/81 100 onsite (2) 5109/774 07/11/80 20 07/24/80 100 Material 08/12/80 480 09/10/80 100 onsite

, 5200/779 01/28/80 6875 05/30/83 85 12/83 01/15/81 48597 03/16/84 57 2780/779 01/28/80 6875 05/30/83 85 05/30/83 11/18/80 20540 01/13/85 23 4

5193/780 01/28/80 729 03/05/82 100 11/81 12/30/81 10501 01/31/83 100 (1)

Estimated man-hours to complete the work for this ECN/DCR.

4 (2) i These man-hours expended are estimates because of costs being accumulated by system rather than by ECN.

i _ --.

L 1

DIVISION OF ENGINEER!?PJ PESIGN DIVISION OF NUCLEAR POWER C019ENTS STA RT MAM-HOUHS COMP . SCH MATRL START MAN-HOURS COMP ECN/*CR DATE To DATE DATE 1 COMP- -DEL DATE DATE TO DATE DATE 1 COMP 2773/780 01/28/80 729 03/05/82 100 '11/81 12/07/82 958 11/04/83 27 5194/781 01/28/80 4400 05/06/83 .100 07/83 05/01/83 721 01/13/85 10 ' Recorder moved from M-30 to M-31 equipment specs.

(1) 5770/781 05/13/83 1600 06/15/83 0 07/83- Unscheduled 0 Unscheduled 0 LECN package is in prepaca-tion.

5195/782 01/28/80 696 03/02/82' 100, 11/81 09/20/81' .8845 04/07/83 100 2775/782 01/28/80 696 03/02/82 100 06/81 04/04/83 2190 11/04/83 15 5110/725 08/11/80 100 02/27/81 100 Material N/A N/A N/A 100 . Field work done under ECN onsite L5311.

5311/785 09/08/80 50 -09/10/80 100 Meterial 09/15/80 605 10/23/81 100 onsite 5331/795 12/01/80 80 01/19/81 .100 Meterial 03/02/81 4 :03/04/81 100 onsite 5478/725 10/21/81 170 10/26/81 100 Material 10/20/81 242 04/22/82 100 =

onsite 5199/737 01/28/80 776 05/24/82 100 Material -02/12/82 38135 03/21/83 100 onsite 2779/787 01/28/80 776 05/24/82 100 Material 12/07/82 15901 11/04/83- 42 onsite 5317/790 09/20/80 273 10/30/81 100 Material 01/19/82 13628 01/31/83 100 onsite 2923/790 09/20/80 273 10/30/81 100 Material 03/30/83 724 11/04/83 42 onsite

DIVISION OF ENGINEERINO DESIGN DTVISION OF NUCLEAR POWER CO M NTS START MAN-HOURS COMP SCH MATRL START MAN-HOURS COMP ECN/DCR DATE TO DATE DATE 5 COMP DEL DATE DATE TO DATE DATE 5 COMP

-- /814 10/10/80 95 01/04/83 100 Material 10/08/80 832 11/22/80 100 Design completion delayed onsite for vendor drawings.

5030/820 08/22/79 1634 04/22/83 100 12/30/83 07/16/82 6786 04/27/83 100 5591/837 01/11/82 592 03/17/83 100 Unknown 10/27/82 461 03/16/84 43 5375/852 01/09/81 135 03/17/81 100 Material 04/02/81 36 04/20/81 100 onsite 5023/855 08/22/79 1567 04/08/81 100 Material 07/06/81 4159 12/31/81 100 This modification was only onsite partially completed and the reuninder was canceled.

5364/879 03/02/81 20 03/30/81 100 Material 06/10/81 832 10/26/81 100 onsite e (2) 5334/895 10/13/80 90 02/05/81 100 Material 02/19/81 200 03/31/81 100 onsite 5333/897 10/10/80 127 02/17/82 100 Material 09/15/80 900 03/31/81 100 onsite .

5328/897 10/07/80 41 01/25/83 100 Material 09/01/80 900 05/18/81 100 onsite 5451/934 06/26/81 518 12/22/82 100 Material 10/13/82 14599 12/31/85 88 Commitment portion of modifi-onsite cation is complete.

(1)

- /936P 03/20/81 3369 Unknown 93 Unknowa Unscheduled 87646 Unscheduled 0 EN DES is reevaluating ATWS due to Sales incident.

- /945 01/23/81 350 08/27/82 100 Material 09/04/82 1664 01/19/83 100 onsite (1)

Estimated man-hours required to complete this ECN/DCR.

(2)

These sian-hours expended are estimates because of costs being accumulated by system rather than by ECN.

m

DIVISION OF EN01NEERING DESIGN DIVISinN OF NUCLEAR POWER COMMENTS STA RT MAN-HOURS COMP - SCH MATRL START. MAN-HOURS COMP ECN/DCR DATE TO DATE DATE 1 COMP DEL DATE DATE TO DATE DATE 1 COMP 5417/946 04/20/81 466 07/12/82 100 Material 08/27/82 ' 6850 c4/26/83 100 onsite i 5357/949 09/14/81 .105 12/30/81 '100 Material 04/25/81 499 05/13/81 100 onsite 5479/954 07/23/81 313 02/02/82 100 Material' N/A N/A N/A N/A Superceded by ECN L5050. l'-

onsite (2) 5444/959 -06/08/81 136 04/06/82 100 Material 06/22/81 150 06/02/82 100 onsite

  • (1) .

-- /972 12/01/80 51350 Unknown 70 Uhknown Uhscheduled 85000 Unscheduled 0

  • Remaining modifications to
  1. satisfy NUREO 0588.

5637/972 03/31/82 281 06/18/82 100 Material 04/15/83 67 04/25 /83 100 r onsite 4 5443/972 06/08/81 14 07/29/81 100 Material 08/01/81 368 10/02/81 100

onsite

' (1) 5420/972 04/28/81 148 05/19/81 100 09/81 Onscheduled 300 unscheduled 0 .

06/29/81 09/11/81 100 03/82 07/21/81 6135 03/16/84 60 5457/972 355 5365/972 12/11/80 30 01/14/81 100 Material 12/12/80 400 06/21/81 100 onsite .

5606/994 03/15/82 394 04/30/82 100 Material 03/22/82 3698 04/05/83 100 onsite 5467/1001 07/17/81 116 02/08/82 100 Material 05/14/82 1179 04/05/83 100 onsite (1)

Estimated man-hours to complete the work for this ECN/DCR.

(2)

These man-hours expended are estimates because of costs being accumulated by system rather than by ECN.

DIVISION OF NUCLEAR POWER COP 94ENTS DIVISION OF ENGINEERING DESIGN START MAN-HOURS COMP SCH MATRL START MAN-HOURS COMP TO DATE DATE $ COMP DEf. DATE DATE TO DATE DATE 1 COMP ECN/DCR DATE 5465/1002 07/17/81 321 02/08/82 100 Material 01/10/82 6519 07/16/82 100 i ensite 5466/1037 07/17/81 91- 04/08/82 100 Material 06/10/82 1857 08/04/82 100 onsite 09/01/81 700 11/05/81 100 Completed on TACPs.

5731/1038 08/02/82 80 12/03/82 100 Material onsite (1) 5408/1057 03/21/81 238 08/27/81 100 Material 08/24/81 1348 04/06/83 100 onsite 5510/1058 08/26/81 146 - 03/22/82 100 Material 04/22/82 2684 05/04/83 100 onsite .

5464/1067 07/17/81 321 04/22/82 100 Material 05/10/82 1846 07/31/82 100 onsite _,

05/11/81 100 N/A 05/20/81 300 06/12/81 100 5411/1090 03/27/81 325 5522/1120 09/09/81 16 03/15/82 100 . Material 09/04/82 3394 01/19/83 100 onsite 5429/1123 04/17/81 3001 07/14/83 98 Material 09/10/82 70968 03/16/84 54 Unit 1 to be cobleted or. site on DCR 1882.

12/18/80 170 04/06/82 100 Material 09/20/82 858 11/04/83 81 5369/1126 onsite l

09/05/81 1059 11/05/81 100 Modirioation completed 2873/1126 09/12/90 170 12/15/80 100 Material onsite before unit 2 initial j criticality.

a 08/10/83 84 08/27/83 04/26/82 32684 01/13/85 22 5193/1152 10/26/81 20999 (1)

Estimeted man-hours to complete the work for this ECN/DCR.

9

s

?.

N DIVISfoN OF ENGINEERING DESIGN DIVISION OF NUCLEAR POWER COMMENTS START MAN. HOURS COMP SCH MATRC" START MAN. HOURS COMP ECN/DCR DATE To DATE DATE- 5 COMP DEL DATE , DATE To DATE DATE $ COMP 06/22/81 06/30/83 04/11/83 443 See Comments 9 To be completed by the 5449/1154 2237 05/31/83 94 end or unit 2, cycle l '

outage.

(1)

-- /1156P 03/22/82 4900 Unknown 34 Unknown Unscheduled 375000 onscheduled . o 5769/1165 10/19/82 442 03/01/83 100 Material 12/11/82 2309 11/04/83 '28 4 onsite (1) 5664/1226 04/28/82 626 02/04/83 100 Material 05/09/83 3994 12/27/83 o onsite ,

(1)

  • 5327/1263 10/03/80 8 03/24/82 100 Phterial 03/17/84 6000 09/17/84 0 onsite (1) .

10/03/80 8 03/24/82 100 Naterial 03/17/84 6000 01/13/85 - o 2938/1263 onsite (1) 02/03/82 01/01/83 100 08/01/83 07/01/83 955 12/27/83 o 5605/1281 29 (1) .

(1)

-- /1304P Unknown 50 Unknown o. Unknown Unscheduled 500 Unscheduled o ,

10/16/81 100 Material 10/01/81 860 10/19/81 100 5536/1308 10/31/81 103 onsite 10/16/81 100 Material 10/12/81 860 10/19/81 100 5537/1308 10/15/81 103 onsite (1) 5304/1326P 08/25/80 800 Unknown 60 Unknown Unscheduled 11220 Unscheduled o 10/20/82 7601 11/04/83 52 Unit 1 is complete.

5684/1370 06/24/82 418 05/06/83 100 Material onsite (1)

Estimated man-hours to complete the work for this ECN/DCR.

W

3 DIVISION OF ENGINEERING DESIGN DIVISION OF NffCLEAR POWER COP 9ENTS START. MAN-HOURS COMP: SCH MATRL STAE' - MAN-HOURS COMP ECN/DCR DATE TO DATE DATE $ COMP DEL DATE . DATE To DATE DATE 1 COMP J

i 5899/1384 03/03/82 20 ' 07/31/83 25 ' Material 01/20/83 See '03/01/83 100 This was a documentation change ensite coaunent only. Field man-hours are

" included under ECN L5604/DCR 1389.

5604/1389 02/02/82 35 05/24/82 100- Material .01/21/83 711~

03/01/83 100

~ '

onsite 5653/1399 .04/15/82 307 04/28/83 100 Material 11/01/82 3043 '12/31/82' 100 onsite i (1) 5709/1467 - 06/28/82 79 11/30/82 100 Unknown 03/17/84 800 10/26/84 0 4

5685/1474 05/26/82 30 07/19/82 100 Material 12/22/82 152 01/05/83 100 ,

onsite .

5674/1482 07/08/82 604 04/14/83 100 Material 05/11/82 18602 03/08/83 100 '

j onsite '

(1) 5410/1518 04/28/81 50 07/19/82 100 Material 03/17/84 244 10/26/84 0 onsite 5726/1534 07/22/82 4 10/14/82 100 Material 12/08/82 11531 04/12/83- 100 Commitment portion completed onsite by 12/21/82. '=

i .i 1 5700/1584 06/16/82 61 03/17/83 100 Material 10/29/82 1842 03/08/83 100 Commaitment portion completed )

onsite by 12/21/82.

l' (1)

L5894/1585 08/26/82 20 Unscheduled 5 Unknown Unscheduled 1500 anscheduled 0 (1) 5773/1645 10/20/82 76 06/30/83 9 02/28/82 08/05/83 4000 03/16/84 0 Analysis schedule is slipping.

See DCR 1808.

j 5790/1650 11/10/82 66 04/21/83 100 Material 12/03/82 106 12/14/32 100 onsite (1) j Estimated man-hours required to complete this ECN/DCR.

h i

1 5

m v w

DIVISION OF NUCLEAR POWER C0peENTS DIVISION OF ENGINEERING DESIGN START MAN-HOURS COMP SCH MATRL START MAN-HOURS COMP ECN/DCR DATE TO DATE DATE 1 COMP DEL DATE DATE TO DATE SE 5 COMP (1) (1) 01/20/83 100 08/15/83 0 09/83 03/17/84 3000 10/26/84 '0 5831/1662 (1) (1)

---/1691P thscheduled 100 thscheduled 0 Unknown thscheduled 5500 Unscheduled. 0 (1) (1)

/1698 06/01/83 32000 thscheduled 0 Unknown Unscheduled 175000 Unscheduled 0

---/1713P thscheduled 0 thse.heduled 0 Unknown Unscheduled 6000 Unscheduled 0 (1) Man-hours are included in 8000 Unschd uled 0 thknown Unscheduled See Comment Unscheduled 0-

---/1730P 07/01/83

. DCR 1698.

(4) (1) thscheduled 0 02/14/83 254 03/01/83 100

--/1739L thscheduled 50 Material '

onsite (4) (1)

--/1806L Uhscheduled 50 thscheduled 0 Material 02/17/83 , 5 02/09/83 100 onsite (1) 60 07/01/83 12 thknown 08/05/83 4500 03/16/84 0 EDS analysis commitments 5856/1808 03/21/83 cor.tinue to's11p.

See ECN L5773 Schedule excludes seat replacement.

04/01/83 100 05/06/83' 05/02/83 400 10/26/84 10 5847/1835 02/23/83 350 (1) (1) 07/01/83 0 06/30/83 07/01/83 2500 11/04/83 0 5871/1856 05/14/83 250 (1) 04/18/84 Material 05/14/83 15000 07/01/84 0

---/1877 04/18/83 100 5 onsite (1) (1) 10/15/83 0 Unknown 12/27/83 4000 03/16/84 0 Unit 1 only

---/1882P 07/01/83 600 (1)

Estimated man-hours to complete the work for this ECN/DCR.

(4)

The L after the DCR signifies that formal design work will follow shortly after the field completes implementation. Design star

  • and completion dates are not needed to ensure that the commitment is met.

e..- __ _

Description' Man-hours Turbine Teardown and Inspection 1980 '26240 Turbine Teardown and Inspection 1982 -82308 Upper Internals Modification- 14607.

Small Break LOCA Analysis 24900 )

i Quality Pressure Ralief Yalves 9450 I l

Leakage reduction Makeup / Letdown System 11600 Probabilistic Risk Assessment 28750 Degraded Task Force 150100 IE Bulletin 79-02 3500 ',

NUREG 0577 Study 5250 NUREG 0612 Study 4200 (1)

Environmental Qualification of Mechanical Equipment 2750000 (1) .

Estimated man-hours to complete the work for this ECN/DCR. .

ENCLOSURE'4-

  • PROGRESS PROJECTIONS 70R SCHEDGLED NRC-RELATED'M'3IFICAT10NS . .

' PRE PRE PRE' U2, C1 U2, C1 U1.C2 VI C2 _ U2, C2 U2. C2 . ,

(PERCENT (PEPCENT (PERCENT (PETCEN1' (PERCENT (PEPCENT .

UNIT, ECN/DCR DESCHIFTION COMPLETE) :s*

COMPLETE)' COMPLETE) . COMPLETE) COMPLETE) . COMPLETE) 5045/D0322 Reactor overpress Instrumentation . 1 0 0 0 100 2 0 100 5106/689 Reactor Water Level Indicator 1 35 35 40 100 2768/689 . Reactor Water Level Indicator 2 2. 5 5 5 45 100 '

5119/706  : Install Radiation Monitor Cable in Conduit 1 Modification will be used as needed for an indefinite period of time.

5196/751 Wide-Range Containment Pressure Monitors 1 0' 0 50 100 l I

2776/751 Wide-Range Containment Pressure Monitors 2 50 100 i

  • 5197/752 Reactor Vessel Head Vent System 1 86 86 86 100 2777/752 Reactor Vessel Hea1 Vent System 2 30 100 5200/779 Postaccident Sampling Paetitty 1 70 . 70 90 100 2780/779 Postaccident Samp1PS racility 2 25 to 40 40 95 100 2773/780 High-Range Effluent Monitors 2 75 100 5194/781 Iodine Radiation Monitors 1 10 15 30 100 2 10 10 10 10 90 100 2775/782 Containment Radiation Monitors 2 60 100 2779/787 Containment Isolation Radiation Monitor 2 80 100 2923/790 High-Range Area Radiation Monitor 2 95 100 5591/837 W-2 Switches 1 50 50 80 100 2 80s too 5457/972 Replace Solenoid Yalves 1 50 50 80 100 2 80 100 5429/1123 H2 Mitigation System (Unit 1 is complete except for remainder of work under DCR 1882) 2 25 100 m

ENCLOSURE 4(Continued).

PRE PRE PRE U2, C1 U2, C1 U1,C2 Ut U2, C2 e C2 U2, C2 (PERCENT (PERCENT - (PERCENT (PEPCENT . (PERCENT (PERCENT MN / DOR DESfBIFIlON DEZI COMPLETE 1 fgg1EIE1 COMPLETE) COMPLEIE) COMPLETE) COMPLETE) 5369/1126 Revise FCV-67-152 Control Logio 0 85 85 85 100 5198/1152 Technical Support Center 1 45 65 80 100 2 30 30 30 30 90 100 i <

5449/1154 Modify Present Degraded Voltage Relay Design -1 10 100 to Comply With the Time Delay Selected Guide- 2 10 100 lines.

Reference:

ECN L5047.

5769/1165 Reroute Chemical Feedlines to AFW (Unit 1 2 65 100 Complete) 5664/1226 Provide Wells Fargo System With Tamper 0 20 20 100 ,

Indicator 5327/1263 Modify RWST Screen and Insulation 1 0 0 0 0 100 2938/1263 Hodify RWST Screen and Insulation 2 0 0 0 0 50 100 5605/1281 Replace 1/2-inch Fire Protection Drops With 1 20 20 100 1-inch Drops 2 20 20 100 5684/1370 BCP Oil Shield (Unit 1 Complete) 2 0 100 5709/1467 Install Switch in Communication Cable for 0 0 0 0 0 100 Redundancy of RUSCO SAL 500 Printers 5410/1518 Add 1 Fire Protection Sprinkler in Unit 1 1 0 0 0 0 100 Reactor Buildits Annulus 5773/1645 Replace PORVs 1 0 0 10 100 2 0 100 5831/1662 Re-evaluation of the Design of the Waste Gas 0 0 0 0 0 100 Analyzers Supplied by Westinghouse 6

' ENCLOSURE 4(Continued)

PRE PRE PRE U2, C1- U2, C1 U1.C2 - U1,' C2 U2, C2 U2, C2 (PERCENT (PERCENT (PERCENT (PERCENT (PERCENT (PERCENT EpfjL. Dy4CJJf7JpN R5ll COMPLETIl COMPLEl u COMPLETE) COMPLETE) COMPLETE) COMPLETE) 5856/1808 Pressurizer Safety Valve Loop Seal Drain Lines 1 0 0 10 100 (This schedule does not include replacing valve. 2 0 100 seats) 5847/1835 Modify the vertical Curtain-Type cravity 0 25 25 30 50 100 Operated Fire Dampers by Adding the Negator ,

Closure Springs and Positive Blades Latching . (.

5871/1856 Relocate ERCW Radiation Monitor 0 30 100

/1877 Fuse Identification 1 20 50 65 80 100 2 20 50 65 80 ,100

/1882P Install Four Additional Ignitors in Upper 1 0 0 10 - 100.

Containment (Unit 1 only) 9 M

6

~

ENCLOSURE 5 .

SQN NRC CONNITHENT SCHEDULE 1983 1981 1985 1990 1987 J F M A M J J A S 0 N O J F M A M J J A S 0 N 9 J F M A 'M J J A $ 0 N O J F M A M J J A S O es D J F M A M J J A $ 0 N O CYCLE I

' :YCLE 4 C'TLE 2 8

, s LMIT 1 8 l g a

SCt(DULE e yg , t3e , e se l 8 8 e e eCYCLE 2 i

CYCLE 3 ' CTCLE 4 i CYCLE 1 -

e UNIT 2 8 l e EN I 91 l 79 '

138  !

e s ,

8 IIELOCATE CLASS IE ELECT C005'LETE 8 e s

' s s e EQUIP l l a L5536/Dl3SS l l s i

RCP OIL SH]ELO UNIT 1 COMPLETE l 8 l

L5604/DI378 I e e i ,

, , l ,

' I l

' 8 RELAY ROOMS EMERC ticp.fi,c CDPFLETE . l l

!, l L5585/DI474 ' s a

' e

' I I l 9 SPENT FUEL CATES  !  !

COPPLETE l 8 8 LE297/DS748 , e 4 8 8 LE725/D0748  : , s REACENT A10 COPPLETE ' s e

"I#

a I L5444/09950 l l s s CONT ISOL RAD MONITCH 77 . UNIT l COPPLETE. ,e i

ts 8 l ,

i L2779/D0787 8

, e s l RM OVERPRESS INSTR 8lg l s 8

i LS84G/00322 a e 8 8

.I .I .O l

' NTED RP- 's =Te i.SS.34..RATEtETERS

. COPPLETE 'l ,

l

. l a e O A CopMITrest DATE DIVISION OF 4ACLEAR POWER SS8C/1EP8 /DClul01 OUTACE w ouTAct gy_,T",,A" SEQUOYAH NUCLEAR PLANT emi on ouTAct , oE,oTE. -, oATE. s/is m

4 I

1 SQN NRC COMMITHENT SCHEDULE 1983 I984 1095 1980 1987 J F M A .e ! 7 A 5 O N O J F et A M J J A G 0 N O J F M A M J J A S 0 N O J F M A N J J A S O N O J F n A M J J A $ 0 N O

' 8 e a e

' CYCLE 3 ' :YCLE 4 CCLE 2 8 DULF yg l Se CYCL 1 eCYCLE 2 , CYCLE 3 . CYCLE 4 UNIT 2 8 l . 8 79 e RE"AERS 95, 133 l ,

3 NPR - IV A 6 - 1 &2 8 (A 7 1 CDP.8LETEl s 8 8 L5317/00798 s 8

2923/00793 l l e l l RX LEVEL 180 s  ; y e l l

. Lsise/oeSa9 '

I 2706/00609 l ,

a l l vlDE RANC CONT PRESS 8 e

MONITORS

  • a ,

,! ' l L5196/DE758 , ' s ,

2776/00758 .

e l ,

l RE VESSEL YENT SYS 8 M E UNIT 1' 'PARTIALLY COPFLETE s '

a

LEIG7/00752 e 2777/D0752 e 8

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