IR 05000289/1982006

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IE Insp Rept 50-289/82-06 on 820413-0511.No Noncompliance Noted.Major Areas Inspected:Previous Insp Findings,Plant Operations During long-term Shutdown Including Facility Log & Tours & RCS Insp & Requalification
ML20054H066
Person / Time
Site: Crane Constellation icon.png
Issue date: 06/04/1982
From: Fasano A, Gray E, Haverkamp D, Nicholas H, Young F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20054H053 List:
References
50-289-82-06, 50-289-82-6, NUDOCS 8206220538
Download: ML20054H066 (32)
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U.S. NUCLEAR REGULATORY COMMISSION Region 1 Report No.

50-289/82-06 Docket No.

50-289 icense No.

DPR-50 Priority Category C

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l censee:

GPU Nuclear Corporation P.O. Box 480 Middletown, Pennsylvania 17057 Facility:

Three Mile Island Nuclear Station, Unit 1 Inspection at: Middletown, Pennsylvania Inspection conducted: April 13, 1982 - May 11, 1982 Inspectors:

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f/2. 8[S E E. Gray, Reactor Inspe fof date signed (April 20-22 and 27-27, 1982)*

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Y2%l?2.

D. Haverkamp, Senior psident Inspector (TMI-1)

date signed Y b h M L 1 93--

Sk/02.

l H. Nicholls,' Reactor Inspector date signed (April 26-28, 1982)*

5/2P/P1 F. Young, Resident In~ ector (TMI-1)

date signed Other NRC C. Sellers, Materials Engineering Branch Personnel:

Division of Engineering, NRR (April 20-22,1982)

R. Jacobs, TMI-l Project Manager, Operating Reactors Branch 4, Division of Licensing, NRR (April 20-21, 1982)

Approved by:

b U, b 6 l 4 l91.

A. Fasano, Chief, Three Mile Island Section date signed Projects Branch No. 2

  • denotes dates of inspection 8206220538 820607 PDR ADOCK 05000289

PDR

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i Inspection Summary:

Inspection on April 13, 1982, - May 11, 1982, (Report Number 50-289/82-07)

Areas Inspected:

Routine safety inspection by resident and regional-based

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inspectors (219 hours0.00253 days <br />0.0608 hours <br />3.621032e-4 weeks <br />8.33295e-5 months <br />) of licensee action on previous inspection findings; plant operations during long term shutdown including facility tours and log,

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and record reviews; reactor coolant system inspections and requalification;

j steam generator eddy current inspection; steam generator recovery program; TMI-l restart preoperational testing; and TMI-I restart modifications - task status.

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Results:

No violations were identified.

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Details 1.

Persons Contacted GPU Nuclear Corporation R. Adamiak, Project Control Manager (TMI-1), Administration C. Adams, Quality Assurance Engineer I, Nuclear Assurance B. Ballard, Manager TMI Quality Assurance Modifications / Operations, Nuclear Assurance R. Barley, Lead Mechanical Engineer TMI-l M. Beers, Engineering Assistant Senior II, Nuclear Assurance D. Bulgarelli, Laboratory Services Manager, Nuclear Assurance J. Colitz, Plant Engineering Director TMI-1 C. Davis, Modification Control Coordinator 0. Deiter, Engineer Assistant Senior II, Nuclear Assurance T. Faulkner, Planning and Scheduling Manager, Maintenance and Construction R. Fenti, Quality Control Manager, Nuclear Assurance J. Fritzen, Technical Functions TMI-l Site Supervisor

  • J. Garrison, QA Engineer Assistant Senior III, Nuclear Assurance S. Giacobbe, Welding and Materials Manager, Nuclear Assurance M. Graham, Engineer, Technical Functions T. Hawkins, Manager IMI-l Startup and Test, Technical Functions H. Henry, Engineer Assistant Senior II, Nuclear Assurance H. Hukill, Vice President and Director TMI-1
  • C. Incorvati, QA Technical Analyst III, Nuclear Assurance J. Jones, Acting Supervisor Training and Educational Development, Nuclear Assurance N. Kazanas, Director of Quality Assurance, Nuclear Assurance R. Knief, Manager Plant Training, Nuclear Assurance
  • S. Levin, Maintenance and Construction Director (TMI-1),

Maintenance and Construction W. Miller, Nuclear Licensing Engineer, Technical Functions M. Nelson, Manager Safety Review-Nuclear, Nuclear Assurance D. Osterhout, Media Representative, Communications J. Potter, Engineer Assistant Senior III, Nuclear Assurance M. Ross, Manager Plant Operations TMI-1 C. Smyth, Supervisor TMI-1 Licensing, Technical Functions

  • C. Stephenson, Nuclear Licensing Engineer, Technical Functions
  • R. Toole, Operations and Maintenance Director TMI-1
  • K. Tremblay, Engineer Assistant Senior II, Nuclear Assurance E. Wallace, Manager PWR Licensing, Technical Functions S. Wilkerson, Lead Nuclear Engineer TMI-1 Babcock & Wilcox H. Behnke, Manager, Reactor Coolant System Component Engineering, Nuclear Power Group

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Catalytic Incorporated V. Haberstroh, Pipefitter General Foreman T. Reddington, Project Superintendent I. Silsbee, Piping Supervisor The inspector also interviewed several other licensee employees during the inspection. They included control room operators, maintenance personnel, engineering staff personnel, and general office personnel.

  • denotes those present at the exit interview 2.

_ Licensee Action on Previous Inspection Findings (0 pen) Inspector Follow Item 289/79-IR-10:

Inadequate Plant Operations Review Committee (PORC) reviews of surveillance procedure changes. This violation was identified for TMI-2 in NRC letter to Metropolitan Edison dated October 25, 1979, and was based on findings described in NUREG-0600,

" Investigation into the March 28, 1979, Three Mile Island Accident by the Office of Inspection and Enforcement," Investigation Report No. 50-320/79-10.

The specific violation, commitments for corrective action applicable to TMI-l and the status of corrective measures completed for TMI-1, were

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described in NRC Region I Inspection Report 50-289/81-17, dated October 23, 1981.

In that report the inspector noted that significant changes in the licensee's safety review process, including elimination of the PORC, were being reviewed by the NRC staff. The inspector then stated that, if the PORC was eliminated, adequate training should be provided to those individuals or groups of individuals who assume review functions previously performed by the PORC. The inspector also noted that the licensee's intent and schedule for training PORC members or other persons who assume their functions needed to be updated.

In the cover letter for Inspection 50-289/81-19, licensee management was requested to inform NRC regional management "of the date by which your PORC training program will be fully.

implemented for Unit 1 and the applicability and implementation of this training to other members of your staff who may be perfonning procedure and safety review functions previously assigned to the PORC".

The licensee responded to the above matter in a letter dated December 8, 1981.

The following revised / updated commitments were included in the licensee's response:

A further training program is being developed which includes (1)

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Technical Specifications use and content, (2) design bases accidents and transients (including AT0G), and (3) TMI-1 non-routine reporting requirements (Tech. Specs.,10 CFR 21, etc.)

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It is anticipated that the training program development will be complete by February 1, 1982, and the first cycle of training will be completed in May, 1982.

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Technical Specification Change Request (TSCR) 1008 proposes to

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change the safety review process, and FORC will no longer be required.

It is anticipated that the above training program will be extended-i to the individuals / groups who conduct reviews pursuant to proposed

Technical Specifications 6.5.1.1 and 6.5.2.1.

The first cycle of j

training will be completed four months after the implementation date.

for TSCR 100B.

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The inspector reviewed the licensee's revised PORC/ Independent Safety i

Review Training Program and its completion status as of May 11, 1982.

The training program was presented in two parts.

Part I included (a)

l PORC and Plant Engineering Group (PEG) Charters, (b) Technical Specifications and (c) non-routine NRC reporting requirements.

Part II included (a)

accident analysis, (b) NRC organization and requirements, and (c) TMI-1 l

organization. Both Parts I and II consisted of approximately four hours l

of formal classroom presentation by various experienced GPU Nuclear

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managers and supervisors. The training was enhanced by providing numerous i

documents (handouts) to review personnel in attendance regarding the following subject matters:

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Non routine Reporting Requirements

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GPU Nuclear memo from P.R. Clark, dated December 17, 1981, "TMI-1

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Implementation of the New GPUN Review and Approval Process"

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THI-1 AP-1034, " Plant Operations Review Committee Charter", Revision 1,

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dated May 20, 1981

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TSCR 1008

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NRC Guidance on Reporting and 10 CFR 50.59 Changes to Facilities,

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Procedures and Tests I

Draft AP-1034, " Plant Engineering Group"'

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TMI-1 Organization to Perform Daily Work

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Licensing Documents / Process / Basis

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NRC Organization Charts

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Safety Review Process Overview of TMI-l Accident Analyses

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Specific Accident Analyses (Steam Line Break, Feed Line Break, LOCA,

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Rod Ejection, Locked Rotor, etc.)

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The eight hour program was conducted three times in March and April 1982, l

and has been attended by 52 of the 62 TMI-l and TMI-2 review personnel identified for training. Ten individuals missed Part I and/or Part II of the program. Of the 24 TMI-l PORC members required to attend, 19 have completed the course. The training program was video-taped during the third presentation of Parts I and II.

Based on review of the above training materials and attendance at the Part I presentation on April 15, 1982, the inspector determined that the PORC/ Independent Safety Review Training Program was substantive, was clearly presented, and exceeded the revised / updated commitments for training program content. However, the inspector noted that the following matters require satisfactory resolution prior to closeout of this item:

(1) TMI-l Training Department Procedure TD4201, dated July 3, 1980, provided a PORC/ safety review training outline that included subjects of Basic Theory, PWR Components and Inter-relationships Safety Limits, Transients, LOCA's, Written Guidelines, and Restart Modifications.

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Most, but not all, of these subjects are consistent with licensee safety review training commitments to the NRC or the current training

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j program content. A training department memo has been drafted that describes the current safety review training program, but the memo was never issued.

These documents require licensee review, revision, and/or issuance.

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(2) TD 4201 requires instructors to prepare and submit quiz questions and answers to the training group supervisor. TD 4201 also requires j

instructors to administer and grade a quiz upon completing the training program.

Quiz questions / answers were not prepared as of

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May 11, 1982. An appropriate quiz, or an alternate measurement of training effectiveness, appears necessary based on TD 4201 requirements.

(3) Although training presentations were substantive and video-taped as

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described above, no lesson plans were prepared, consistent with training department requirements / practices.

Such lesson plans l

appear particularly essential during makeup /new employee training using video tapes and training handouts.

(4) Although numerous potential safety review personnel have been identified I

for training, certain key individuals have not been designated including the Vice President TMI-1, Quality Assurance / Control Department Onsite Managers, Independent Onsite Safety Review Group (IOSRG)

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members, and Shift Supervisors / Foremen. These individuals should be (

considered for safety review training.

l (5) The PORC/ Independent Safety Review Training Program has not been

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attended by all licensee identified individuals (5 PORC members and 10 safety reviewers).

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The inspector discussed the above matters with licensee plant, safety review, and training managers.

Licensee evaluation and action regarding these matters will be reviewed during a subsequent NRC inspection.

(Closed) Inspector Follow Item 289/80-19-06:

Implement Test Instruction 10,

" Training and Qualifications of Test Personnel," and assign qualified test personnel. The inspector reviewed TMI-1 Administrative Procedure 1047, "Startup and Test Manual," Revision 1, dated January 9, 1982, and TMI-l Test Instruction 10, Revision 1, " Training and Qualification of Personnel," dated August 18, 1981.

The instruction established the training and qualification requirements for Startup Test Engineers who conduct preoperational and startup test. The inspector reviewed Training and Qualification General Data Sheets for four Startup and Test Engineers.

All requirements for education, training and qualification were met. The inspector had no further comments concerning this item.

(Closed) Unresolved Item 289/82-03-01:

Steam Generator level detector as-built drawing discrepancies associated with Modification Task RM-8.

Notes describing the proper support of the piping runs did not correctly reflect the specific design criteria used in building the unmodified portion of the piping during initial construction.

The licensee has submitted Field Questionnaire 3612 which reflects the correct design criteria.

In addition, the licensee has submitted Field Questionnaire 3611 to better clarify another drawing note concerning proper support af valves in piping runs. The inspector reviewed the above field questionnaire changes with the licensee representatives and found the drawing clarifications adequately addressed the concern.

Based on satisfactory resolution of this item, Task RM-8 installation is considered acceptable.

3.

Plant Operations During Long Term Shutdown a.

Plant Status During Inspection Period

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The plant remained in the cold shutdown condition with Reactor Coolant System (RCS) temperature less than 200 F per NRC order of l

August 9, 1979. On April 13, 1982, the RCS was at 100 F and 0 psig with cooling to the reactor supplied by the "A" Decay Heat Removal l

(DHR) loop.

The RCS was partially drained for eddy current testing l

and reactor vessel internals inspection. The reactor vessel head was l

removed and placed on its storage stand.

Both Once Through Steam

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Generators (OTSG's) were in full wet layup.

During this inspection the following major plant changes or evolutions occurred.

April 14, 1982:

Filled the deep end of the fuel transfer canal

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to the freeboard

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April 15, 1982:

Placed the Upper Plenum in the deep end of the fuel transfer canal l

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April 16, 1982:

RM-A8 (auxiliary and fuel handling builrling)

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air particulate detector taken out of service for I&C mainte-nance

April 18, 1982:

RM-A8 returned to service

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I April 26, 1982: Withdrew and visually inspected two fuel

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assemblies one at a time.

Completed visual inspection of fuel assemblies and returned assemblies to proper position in the core April 29, 1982: Withdrew and visually inspected two control

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rods.

Control rods were returned to fuel assemblies

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April 30, 1982:

Declared an unusual event due to potentially

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contaminated man being injured and taken to Hershey Medical Center (Unusual Event lasted 23 minutes)

May 4, 1982:

RM-A9, Reactor Building Purge Air Particulate

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i Monitor, failed and taken out of service

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May 5, 1982:

RM-A9 raturned to service

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May 6, 1982:

Reactor vessel head reseated on top of the vessel May 7, 1982:

Pumped the deep end of fuel transfer canal dry

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May 7, 1982: Borated Water Storage Tank (BWST) placed on

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cleanup to remove sulfur

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May 8, 1982: BWST taken off cleanup

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At the close of this inspection period the RCS was at 100 F and 0 psig with cooling to the reactor core from "A" DHR loop. The RCS

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was partially drained in preparation for steam generator tube removal.

t Both OTSG's were in full wet layup.

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Plant Logs and Operating Records

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The inspector reviewed selected portions of the following plant

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procedures to determine the licensee established requirements in

this area in preparation for a review of selected logs and records.

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Administrative Procedure (AP) 1007, " Control of Records,"

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AP 1012, " Shift Relief and Log Entries," Revision 14 AP 1033, " Operating Memos and Standing Orders," Revision 2

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AP 1044, " Event Review and Reporting Requirements," Revision 2

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The inspector reviewed the following plant logs and operating records.

Shift Foreman Log and Control Room Log Book

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Shift Turnover Checklist

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Temporary Change Notice (TCN) Log Book

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l Active Tagging Application Book

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Plant logs and operating records were reviewed to verify the following items.

Log keeping practices and log book reviews are conducted in

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accordance with established administrative controls, i

Log entries involving abnormal conditions provide sufficient

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detail to communicate equipment status, lockout status, correction

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and restoration.

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Operating orders do not conflict with Technical Specification

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(TS) requirements.

No violations were identified.

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Facility Tours

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The inspector toured the following plant areas.

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Control Room (daily)

Auxiliary Building (April 14)

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Intermediate Building (May 7)

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Vital Switchgear Rooms (April 21, May 7)

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Diesel Generator Building (April 19, May 3)

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Site Perimeter (May 5)

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Reactor Building (April 13, 14, 16, 20, 26, 27, and 29, May 3,

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The following observations / discussions / determinations were made.

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Control room annunciators:

Selected lighted annunciators

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(Radiation Level HI, RM-G9 Fuel Handling Bridge Radiation monitor, BWST Tank Level HI/LO, Penetration Pressurization System Pressure) were discussed with control room operators to verify that the reason for annunciation was understood and corrective action, if required, was being taken.

Control room manning: The inspector verified that control room

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manning requirements of 10 CFR 50.54(k) and the Technical Specifications were being met.

In addition, the inspector observed shift turnovers to verify that continuity of system status was maintained.

Technical Specifications: Through log review and direct observation,

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the inspector verified compliance with Technical Specifications associated with fuel movement and steam generator tube inspection requirements during shutdown plant operation.

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Plant housekeeping conditions: Unsatisfactory plant house-keeping conditions observed by the inspector had been identified previously by station personnel and corrective action had been initiated as necessary.

Monitoring instrumentation: The inspector verified that spent

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fuel pool level, decay heat removal flow, and plant effluent flow instrumentation were functional and indicated that parameters were within Technical Specification limits.

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Valve positions: The inspector veriffad that selected valves were in the position or condition required by Technical Specifi-cations for the applicable plant mode. This verification included control board indication and field observation of valve positions for the emergency feedwater and decay heat closed cycle cooling systems.

Security:

The inspector verified that protected and vital area

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security requirements were met. The verification included observations of access controls, boundary integrity, and search, escort and badging practices.

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Licensee meetings: The inspector frequently attended the OTSG status meetings, Plan-of-the-Day (POD) morning meetings and the daily plant status afternoon meetings held by licensee management and supervisory personnel. The inspector assessed licensee evaluation of plant conditions, status and problems and reviewed licensee plans for conducting certain major plant operations and maintenance activities.

The inspector also attended bi-weekly project status meetings to assess licensee progress and difficulties related to plant modifications required for restar.

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I Acceptance crite.fa for the above items included inspector judgement and requirements of 10 CFR 50.54(k), Regulatory Guide 1.114, Technical Specifications, and the following procedures.

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AP 1002, " Rules for the Protection of Employees Working on Electrical and Mechanical Apparatus," Revision 22 AP 1008, " Good Housekeeping," Revision 7

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AP 1037, " Control of Caution and DNO Tags," Revision 2 No violations were identified.

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Reactor Coolant System Inspections and Requalification a.

RCS Inspection Plan During April 20-22, and 27-29, 1982, NRC Region I inspectors and NRR staff members reviewed and evaluated the licensee's inspection plan

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for the various components in the TMI-l reactor coolant system (RCS)

to determine the suitability of the components for continued use.

The NRC reviewers included the resident inspectors, a reactor inspector (NRC Region I metallurgist), a materials engineer (NRR), and the TMI-l project manager (NRR).

The inspection plan was described in Babcock & Wilcox Report BAW-1727, "TMI-l Steam Generator Recovery Program Task 7 Reactor Coolant System Inspections and Requalification,"

dated April 16, 1982.

The report provided:

(1) the objectives and scope of work involved, (2) a summary of failure analysis information from Task 1 of the TMI-l steam generator recovery program as known to date (see NRC Region I Inspection Report 50-289/82-03, paragraph 3.a for additional details concerning Task 1), (3) the factors / assumptions and the approach used to develop the test plan, a summary of the

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materials used in the RCS components and an evaluation of their susceptibility to attack, and (4) a description of the recommended

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inspections and tests to qualify the components. The specific inspection and test requirements, test conditions, and acceptance criteria for each component were provided in engineering information records included in the appendix to BAW-1727.

i The inspection plan included inspections and tests of 22 items as identified below.

Items to be inspected Type of Inspection (1) OTSG Stainless Steel (SS) cladding, Dye penetrant, upper and lower heads wipe sample (2) OTSG Inconel cladding, upper, and Dye penetrant, lower tubesheets wipe sample

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-12 (3) Makeup nozzle safe-end, HPI nozzle Radiograph and safe-ends, spray line pressurizer ultrasonic examination nozzle safe-ends, surge line pressurizer nozzle safe-end (4) Leadscrew Wipe samples, visual (5) Reactor vessel (RV) inner 0-ring Lab metallographic, investigation, dye penetrant, wipe sample of 0-ring and underside of closure head (6) Motor tube Ultrasonic (7) Control rod drive mechanism (CRDM)

Dye penetrant, lab

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end fitting metallography, wipe sample per Task 1

(8) Holddown bolts of plenum lift lugs Ultrasonic (9) Top of core and control components Video

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(10). Fuel assembly, control components Video (11) Regenerative Neutron Source (RNS)

Dye penetrant, lab.

retainer metallography (12) Core support shield-to-core barrel Ultrasonic boles

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(13) Lower bolting rings in RV internals Video and lower vessel head

(14) Reactor internals baffle plate Video region

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(15) CRDM nozzles to SS flange Eddy-current (16) Plenum assembly Video of accessible portions on plenum stand in deep end of l

fuel transfer canal l

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plenum cylinder to plenum Ultrasonic where i

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(18) Vent valves and core support shield Video, Tech. Spec.

exercise (19) Low pressure injection pipe welds Ultrasonic (selected welds)

(20) Incore detectors Functional (21) Incore detector sheath Dye penetrant, wipe sample (22) Vent valve thermocouple nozzle Eddy-current Based on a comprehensive review of BAW-1727 and its appended engineering information records, discussions with licensee / contractor management and test personnel, and review of qualification procedures and records, the RCS inspection and qualification program is considered technically adequate.

However, BAW-1727 appears incomplete or inaccurate regarding the following three items.

(1) Page 9-1 describes welds which were heat-treated at 825 F for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

Page 10-4 describes the same welds which were heat-treated at 850 F for 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.

(2) The inspection description for destructive examination of the inner RV 0-ring requires a thorough characterization to demonstrate that the most susceptible areas (areas under greatest tension)

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for attack have been examined.

(3) The significance of video tape as an official archive record is not described.

NRC Region I management discussed the above determinations with licensee management during a telephone conversation on May 6, 1982.

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Llcensee management acknowledged the comments and stated that BAW-1727 i

would be revised as necessary.

Licensee management further stated that all preliminary inspection evaluations appeared acceptable.

GPU Nuclear Technical Evaluation Report (TER) of the completed RCS inspection and requalification program, including BAW-1727 and inspection results, was expected to be issued by late May 1982. The i

TER will be reviewed during a subsequent NRC Region I inspection (289/82-06-01).

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RCS Inspections - Implementation Review l

The inspectors reviewed and witnessed selected evolutions /examina-tions related to the RCS inspection and requalification program.

The review was conducted to verify the following items.

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Core monitoring during fuel movement met Technical Specifi-

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cation requirements Vessel water level was maintained as required by Technical

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Specifications

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Required administrative approvals were obtained prior to initiating the work Activities were being accomplished by qualified personnel

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Radiological controls were adequate and were properly implemented

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Surveillance on required equipment was properly performed prior

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to use

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Inspeations were made in accordance with the specifications of the licensee's procedures

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Procedures used were adequate to control the activity

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Provisions for maintaining cleanliness areas were adequate The inspectors reviewed the following documents to verify acceptable procedural controls for program implementation.

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ALARA review conducted for reactor vessel head removal, fuel inspection and upper plenum removal Radiation Work Permits (RWP's) associated with special fuel

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inspection and reactor vessel head removal Refueling Procedure (RP) 1501-1, " Fuel Loading Limits and

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Precautions," Revision 4, including Temporary Change Notice (TCN) 1-82-0050

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RP 1502-1, " Refueling Operations," Revision 8, including TCN 1-82-0043

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RP 1505-1, " Core Assembly," Revision 7

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RP 1505-3, "Special Precautions for Fuel Handling," Revision 1 RP 1506-1, " Reactor Upper Plenum Installation," Revision 2

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RP 1506-2, " Closure Head Installation," Revision 1

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RP 1507-3, " Main Fuel Handling Bridge Operating Instructions,"

Revision 6

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RP 1507-12 " Visual Inspection of Fuel Assemblies," Revision 1,

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including TCN 1-82-0081 The inspector witnessed portions of the following evolutions to determine acceptable implementation of the RCS inspection and requalification program.

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April 13, 1982:

Reactor vessel head removal and storage April 15, 1982: Video inspection of upper plenum assembly

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April 21, 1982: Video inspection of the reactor vessel vent

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valves and portions of vent valve surveillance April 26, 1982: Withdrawal, video inspection of two fuel

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assemblies, and replacement of fuel assemblies in the core April 29, 1982: Withdrawal and video inspection of control rod

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May 6, 1982:

Reseating of the reactor vessel head on top of the vessel The overall implementation of the RCS inspection and requalification program was conducted in a professional and competent manner. The inspectors observed effective management direction and coordination between the various functional disciplines which performed or supported the RCS inspections. Command and control during the fuel assembly movements and inspections was particularly effective.

No violations were identified during thd above reviews / observations, however, a poor operating practice was noted on one occasion.

During licensee preparation for video inspection of two fuel assemblies on April 26, 1982, several pieces of heavy video equipment were installed on the main fuel handling bridge (FHB), while the FHB was positioned directly over the unprotected reactor vessel. Although nothing was dropped from the FHB into the reactor vessel, the inspector noted the potential for such an occurrence during other inspection operations. The inspector discussed this concern with the Manager i

Plant Operations TMI-1 and observed additional movement of equipment i

on and off the FHB. All subsequent transferring of equipment witnessed was done with the FHB fully parked at the end of the fuel transfer canal and not over the vessel. The inspector determined that prompt action had been taken regarding this concern.

5.

Steam Generator Eddy Current Inspection During the months of December 1981, to April 1982, the licensee has conducted an extensive eddy current test program to determine the extent of degradation of tubes in both OTSG's (see NRC Region I Inspection

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Reports 50-289/81-32, 50-289/82-01 and 50-289/82-02).

The inspector has continued to monitor the eddy current test program.

The inspector reviewed selected sections of eddy current test program documents and observed field operations of the eddy current inspection personnel on several occasions.

The inspector interviewed several licensee and contractor personnel and determined that they demonstrated adequate knowledge and control over the work being accomplished. No violations were identified.

6.

Steam Generator Recovery Program On April 28, 1982, the resident inspectors and an NRC Region I inspector visited the GPU Materials Laboratory in Reading, Pennsylvania. The purpose of the visit was to determine the laboratory capabilities for materials and chemistry testing, particularly regarding any tasks associated with the TMI-l Steam Generator Recovery Program. The visit included observation of laboratory facilities and equipment and discussions with the Laboratory Services Manager and the Welding and Materials Manager. The inspectors determined that no direct laboratory test support has been provided for Steam Generatory Recovery Program tasks, because the facilities are not designed for testing radioactive materials. The visit was nevertheless useful in identifying the capabilities for testing and analysis of non-radioactive components, fluids and lubricants.

During discussions with the Welding and Materials Manager, the inspectors were informed of tentative plans regarding the ongoing Steam Generator Repair Program. Ten additional tubes sections will be removed from the steam generators during May 1982. Two of these tubes will be removed down to the ninth tube support plate. The tube sections will be used for destructive examinations to obtain additional data for Task 1 - Failure Analysis and Task 4 - Eddy Current Inspection (See NRC Region I Inspection Report 50-289/82-03).

During June 1982 about 150 tubes, including the 10 tubes described above and those tubes with eddy current indications below the upper tube sheet, will be stabilized and/or plugged.

With respect to the long term repair program (Task 2), the following

!

sequence of activities is currently anticipated:

(1) Drain secondary water from OTSG's (mid-June 1982)

,

(2) Fill secondary side of OTSG's with high pH water (3)

Flush crevices with OTSG on recirculation (4) Dry out crevices

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(5) Hydrolance primary side of 0TSG tubes (6) Explosive expansion repair (late July 1982)

(7) Hydrolance (8) Fill secondary side of OTSG's (9) 150# leak (drip) test (10) 150# bubble test (11) Repair leaky tubes as necessary (12) Normal heatup - 1500 psi AP test (13) Other tests (to be determined)

These activities will be reviewed during subsequent NRC Region I inspections.

7.

TMI-l Restart Preoperational Testing a.

Overall Preoperational Test Program The inspector reviewed the overall preoperational testing program for TMI-l restart with the Manager Startup and Test TMI-l and the Supervisor Startup and Test TMI-l to determine completion status of test procedure preparation, test performance and test results evaluation.

The licensee representatives discussed some of the problems and discrepancies identified by startup and test personnel during preoperational equipment calibrations and functional tests recently completed or in progress.

The inspector noted that several preoperational test procedures and the revised Startup and Test Manual had been approved since the last inspection of this area.

Some additional preoperational testing had also been completed. The scope and findings of the inspector's review of these items are described below, b.

Startup and Test Manual Review The inspector reviewed TMI-1 Administrative Procedure 1047, "Startup and Test Manual," Revision 1, dated January 9, 1982.

Changes to the procedure included deletions, additions, corrections of typograph-ical errors, title changes of individuals, and the addition of a test instruction, TI-12, "Non-Modified Systems Functional Tests."

The inspector noted the changes were mostly administrative and did not reduce the scope of the Startup and Test Program.

The inspector determined that the revised program was acceptable.

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c.

Preooerational Test Procedure Review (1) General The inspector reviewed two functional test procedures, related to facility modifications (listed below) which are required to be completed prior to TMI-l restart, to verity that adequate testing would be provided consistent with the following items.

Licensee commitments stated in the TMI-1 Restart Report,

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" Report in Response to NRC Staff - Recommended Require-ments for Restart of Three Mile Island Nuclear Station Unit 1" Requirements delineated in NUREG-0680 (and supplements 1,

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2, and 3), "TMI-1 Restart Evaluation Report," to comply with NRC Order of August 9, 1979

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Licensee commitments stated in the TMI-l Restart Test Planning Specification, Revision 0, dated April 8, 1981

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Applicable regulatory guides

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The licensee's Quality Assurance Program Applicable licensee procedures for preoperational testing

--

For each of the listed modifications the inspector verified that the modification task would be demonstrated acceptable for restart operation by an appropriate functional test. The inspector reviewed each test procedure for (1) technical /

administrative adequacy of management review and approval, (2) procedure format, (3) test objectives (clearly stated and met), (4) prerequisites, (5) environmental conditions, (6) acceptance criteria, (7) technical references, (8) initial conditions, (9) test performance documentation and verification, (10) detailed instructions for performance of test, (11) recording details of conduct of test, (12) restoration of systems to normal after test, (13) identification of personnel conducting test and evaluating test data, and (14) independent verification of critical steps or parameters.

Specific modification tasks, modification design references, and preoperational test procedures reviewed by the inspector are identified below.

(2) Modification Task RM-12 Hydrogen Recombiner References

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TMI-l Restart Report Sections 2.1.1.4 and 11.2.4 i

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NUREG 0680, Item 8-2.1.5.a, Dedicated Recombiner Penetrations

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The inspector reviewed TP 243/1, Revision 0, " Hydrogen Recombiner,"

approved January 28, 1982. TP 243/1 provides an appropriate functional test to demonstrate the operability of the hydrogen recombiner by verification of the operation of the heater element, positive displacement blower,' automatic temperature regulating control, air blast heat exchanger fan, isolation valves, control room alarms and indicators, and recombiner control panel alarms and indicators.

(3) Modification Task LM-21a RCS High Point Vents - Pressurizer References TMI-l Restart Report Section 2.1.2.2

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NUREG 0680, Item LT Additional #4, RCS Venting The inspector reviewed TP 675/1, Revision 0, "RCS High Point Vent," approved April 1, 1982.

TP 675/1 provides an appropriate functional test to demonstrate vent valve operation under expected service conditions, operability of flow /no flow indication, and capability to close under full flow conditions.

(4)

Findings The inspector determined that each of the preoperational test procedures was technically and administratively adequate. No discrepancies were noted in the review of these procedures.

d.

Preoperational Test Results Evaluation The inspector reviewed six completed test procedures (listed below)

to ascertain whether uniform criteria are being applied for evaluating completed preoperational tests to assure their technical and

,

administrative adequacy.

TP 247/2, Revision 0, (test results evaluation approved

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August 24, 1981), " Industrial Cooler Chemical Addition" TP 248/1, Revision 0, (test results evaluation approved

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April 1, 1982), " Backup Instrument Air"

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TP 376/2, Revision 0, (test results evaluation approved February 25, 1982), " Reactor Protection System Trip on Turbine /Feedwater"

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TP 600/1, Revision 0, (test results evaluation approved

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March 18, 1982), " Controlling Procedure for Hot Functional Testing" TP 600/3, Revision 0, (test results evaluation approved

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March 18, 1982), " Thermal Expansion Checks for Hangers, Supports and Restraints" TP 674/1, Revision 0, (test results evaluation approved

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March 18,1982), " Reactor Coolant Pump Operation and Flow Test" The inspector reviewed the test results and verified licensee evaluation of test results by review of (1) test changes, (2) test exceptions, (3) test deficiencies, (4) "as-run" copy of test procedure, (5) QA inspection records, and (6) test result evaluations and approvals.

No discrepancies were noted during review of the above completed test procedures and evaluation of test results, e.

Generic Procedure Review The inspector reviewed six procedures (listed below) that are general in nature and that are used during the startup and testing portion of the TMI-1 Restart Program to support construction testing of modification tasks.

--

TP 250/1, " Generic Instrumentation Testing Procedure," Revision 0, dated December 18, 1981

.

TP 250/2, "Preoperational Startup Testing of Electrical Equip-

--

ment," per Maintenance Procedure (MP) 1420-EL-2, Revision 0, i

dated August 7, 1979

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TP 250/3, " General Procedure for Hydrostatic Testing of Systems and Components," per MP 1410-Y-50, Revision 1, dated July 17, 1981

,

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TP 250/4, " General Procedure for Flushing Piping Systems," per MP 1410-Y-51, Revision 1, dated August 15, 1981

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TP 250/5, "Preoperational Startup Testing of Mechanical Equip-ment," per MP 1410-Y-52, Revision 1, dated September 19, 1981

--

AP 1002, " Rules for the Protection of Employees Working on Electrical and Mechanical Apparatus," Revision 23, dated

'

l May 26, 1981 i

The inspector reviewed the above procedures for their applicability, l

depth, and completeness in supplementing preoperational functional

!

test procedures and in demonstrating acceptable conduct and controls during construction testing of modification tasks.

No discrepancies wers noted:

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8.

TMI-1 Restart Modifications - Task Status

,

The inspector held discussions with licensee management representatives and reviewed licensee scheduling / status documentation for facility modf-fications, which are required to be completed prior to or following TMI-1 restart. The purpose of the review was to determine that modification task completion status (completed /in progress / scheduled, etc.) was consistent with commitments and requirements delineated in the following documents.

TMI-l Restart Report, " Report in Response to NRC Staff - Recommended

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Requirements for Restart of Three Mile Island Nuclear Station Unit 1"

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NUREG 0680 (and Supplements 1, 2, and 3) "TMI-1 Restart Evaluation Report," to comply with NRC Order of August 9, 1979 NRC letter to Met-Ed dated April 22, 1981, " Safety Evaluation Reports

!

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for Items Contained in NUREG 0694"

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NRC letter to Met-Ed dated April 22, 1981, " Safety Evaluation Reports for Items Contained in Enclosure 1 to NUREG 0737"

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NUREG 0746 (and Supplement 1), " Emergency Preparedness Evaluation

'

for TMI-1" NUREG 0752 (and Supplement 1), " Control Room Design Review Report

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for TMI-1"

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ASLB Partial Initial Decision dated August 27, 1981, " Procedural Background and Management Issues"

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ASLB Partial Initial Decision dated December 14, 1981, " Plant Design and Procedures and Separation Issues"

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ASLB Partial Initial Decision dated December 14, 1981, " Emergency Planning Issues"

--

selected IE Bulletins and related licensee responses

--

selected licensee event reports and related Technical Specifications

--

selected License Orders and Technical Specifications Amendments

!

The findings of the modifications task status review are summarized in the attached TMI-1 Modifications Cross Reference Listing - Task to Require-ment, Revision 3, dated May 11, 1982. Modification status for each task is identified on that listing by indicating the modification completion progress according to the following categories: engineering, installation, QC inspection, testing, incomplete work list (IWL) items, at plant, and accepted. Modification inspection status is also summarized in the attachment. As of May 11, 1982, 20 of the 86 modification tasks currently

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required for TMI-1 restart have been completed. The attachment will be updated approximately monthly, and modification task status information will be provided in applicable NRC Region I inspection reports.

i 9.

Exit Interview Meetings were held with senior facility management periodically during the course of the inspection to discuss the inspection scope and findings.

-

The inspectors met with the licensee representatives (denoted in paragraph 1)

t at the conclusion of the inspection on May 11, 1982, and summarized the purpose and scope of the inspection and the findings. The licensee representatives acknowledged the findings.

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TMI-l MODIFICATIONS Revision 3 LROSS REFEREf1CE LISTING May 11, 1982

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(TASK TO REQUIREMENT)

Page 1 of 10 NRC MJDIFICATI0fi INSPECTION TASK NO.

B/A NO.

DESCRIPTION REQUIREMENT STATUS STATUS

  • EM-7 412069 Evaluate and Modify TMI-l Block Walls IE Bulletin Installation /

Partially 80-11 Accepted Completed

  • LM-1/

412044 TSAT Meter Indicator and Alarm flVREG-0680 At Plant /

Partially LM-38 (8-2.1.3.b)

Accepted Completed

  • LM-2 412044 RCS Wide Range Temperature NUREG-0680 At Plant Partially (8-2.1.3.b)

Completed

  • LM-7A 412073 RB Spray Sy. stem Modifications TSCR No. 107/

IWL Items None TSA No. (TBD)

None

(LT. Add'l #2)

IWL Items l

l

  • LM-9 120002 Raise Pressucizer Level Transmitter PID (IIT, Accepted None l

5 1174)

  • LM-13A 412024 Emergency Feedwater Cavitating Venturies flUREG-0680 At Plant Completed except l

(8-2.1.7.a)

IWL/ Testing

'

  • LM-13B 412024 Remove FW Latch from EF-V30A/B PID (IIQ, Engineering None l

1 1064)

+ LM-13X 412024 EFW - Redundant Control and Block Valves NUREG-0680 Engineering N/A (8-2.1.7.a)

+ LM-13X 412024 EFW Auto Start - Low OTSG Level NUREG-0680 Engineering N/A l

(8-2.1.7.a)

+ LM-13X 412155 Isolation of Main Feedwater on OTSG Overfill PID (IIQ, Engineering N/A i 1037)

+ LM-13X 412024 Upgrade Main Steam Rupture Detection System PID (IIQ, Engineering N/A i 1037)

NOTE:

See last page for explanation of modification status symbols and categorie.

TMI-1 MODIFICATIONS Revision 3 CROSS REFERENCE LISTING May 11, 1982

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(TASK TO REQUIREMENT)

Page 2 of 10 NRC MODIFICATION INSPECTION TASK NO.

B/A NO.

DESCRIPTION REQUIREMENT STATUS STATUS

  • LM-16 412001 Fuel Handling Building Isolation /HVAC Chase NUREG-0680 (4)

IWL Items /

None Accepted o LM-16A 412001 Fuel Handling Building Isolation Damper Control NUREG-0680 (4)

Test /IWL Items None

+ LM-16B 412336 Fuel Handling Building ESF Ventilation System NUREG-0680 (4)

Engineering N/A

  • LM-21A 4i2021 RCS High Point Vents - Pressurizer NUREG-0680 Installation /

None (LT Add'l #4)

QC Inspection

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+ LM-21B 412011 RCS High Point Vents - RB Elect Penetration NUREG-0680 On Hold N/A (LT Add'l #4)

+ LM-21B 412021 RCS High Point Vents - Hot Legs /RV Head NUREG-0680 On Hold N/A (LT Add'l #4)

  • LM-23 412013 High Range Containment Monitoring NUREG-0680 Installation /

Partially (8-2.1.8.b)

QC Inspection Completed

  • LM-24A 412032 Post Accident RCS Sampling (Pzr. Sample Bomb)

NUREG-0680 On Hold N/A (8-2.1.8.a)

  • LM-24A 412032 Post Accident RCS Sampling (Shielding)

NUREG-0680 IWL Items Partially (8-2.1.6.b)

Completed o LM-24B 412032 Post Accident RB Atmosphere Sampling NUREG-0680 Installation /

None (8-2.1.8.a)

IWL Items l

  • LM-25A 412013 Post Accident Effluent Monitoring - Gaseous NUREG-0680 IWL Items None (8-2.1.8.b)

o LM-25B 412013 Post Accident Effluent Monitoring - Iodine /Part. NUREG-0680 IWL Items None (8-2.1.8.b)

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TMI-1 MODIFICATIONS Revision 3 CROSS REFERENCE LISTING Mcy 11, 1982

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(TASK TO REQUIREMENT)

Page 3 of 10 NRC MODIFICATION INSPECTION TASK NO.

B/A NO.

DESCRIPTION REQUIREMENT STATUS STATUS

  • LM-26A 412013 Post Accident Containment Pressure Indication NUREG-0680 Installation /

None (LT Add'l #1)

QC Inspection

None Hydrogen (LT Add'l #3)

Installation

  • LM-29 412064 High Rad. Monitoring Alarm System NUREG-0746 Testing None Improvements (II. H)

6 LM-30 412087 Automatic Reactor Coolant Pump Trip NUREG-0680 Engineering N/A (79-05C LT #1)

  • LM-32 412059 Loads of Safeguard (IE) Buses Tech. Specs.

Accepted None (LER80-01)

  • LM-32A 412059 1B E.S. MCC Feed Breaker Upgrade Tech. Specs.

Installation None (LER80-01)

+ LM-38 412017 Remote Shutdown Panels Appendix R Engineering N/A

  • LM-42 412008 Decay Heat Check Valve Leakage Monitor License Order IWL Items /

None (4/20/81)

At Plant

Completed f

  • LM-43B 412028 Atm. Dump / Pressurizer Spray / Turbine Bypass IE Bulletin IWL Items /

None Valves 79-27 At Plant

  • LM-43C/ 412028 Indication of Critical Plant Parameters IE Bulletin IWL Items /

None LM-38 79-27 Testing

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TMI-l MODIFICATIONS Revision 3 CROSS REFERENCE LISTING May 11, 1982

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(TASK TO REQUIREMEriT)

Page 4 of 10 NRC MODIFICATION INSPECTION TASK NO.

B/A NO.

DESCRIPTION REQUIREMEriT STATUS STATUS

  • LM-51A 412020 Shielding Design Review Modifications NUREG-0680 IWL Items None (8-2.1.6.b)
  • LS-6 412015 Control Room Control Console Arrangement NUREG-0752 (5)

Installation None

  • JT-XX 113202 Hard Piping for Hittman Solidification System NUREG-0680 (4)

Installation None

  • fiM-17 120002 IGSCC (Pipe Cracks)

IE Bulletin At Plant Partially

/9-17 Completed

  • NM-31 412342 Anchor Bolt Inspections and Repairs IE Bulletin Installation /

Partially 79-02 Accepted Completed

  • NM-34 120002 480V Bus Trip TSCR No. 60A/

Accepted None TSA No. 70

  • NM-35 412342 Pipe Support Location Inspection and Repairs IE Bulletin Installation /

Partially (Safety Factor 3*2)

79-14 Accepted Completed

  • NM-39 412191 Foundation for Hittman Solidification System NUREG-0680 (4)

Accepted Completed

  • NM-40 412041 Fire Protection TS Amendment Installation /

Partially No. 50/ App. R Accepted Completed

+ NM-41 432009 Perimeter Security Modifications Proposed Security Installation /

None Plan Rev.

Testing

  • NM-47 412086 Control Room Emergency Phone (Hot Line)

NUREG-0746 At Plant None (II.F)

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TMI-l MODIFICATIONS Revision 3 CROSS REFERENCE LISTING May 11,1982

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(TASK TO REQUIREMENT)

Page 5 of 10 NRC MODIFICATION INSPECTION TASK NO.

8/A NO.

DESCRIPTION REQUIREMENT STATUS STATUS

  • NM-48 412010 Seismic Supports for Conduit NUREG-0680 Installation /

None (various)

Accepted

  • NM-49 120002 Modify Internals:

Crane Tilting Disc Tech. Specs.

QC Inspection Partially Check Valves (LER 80-03)

Completed

  • NM-51 120002 Modify Internals:

Feedwater to OTSG Tech. Specs.

Accepted Partially Check Valves (LER 80-03)

Completed

  • PM-1 412060 Replace Containment Isol. Va've RB-V7 Tech. Specs.

At Plant /

Completed (LER'80-07)

Accepted

  • PM-3 412074 Purge and Vent Valves (0 pen Limits)

NUREG-0737 Installation None (SER II.E.4.2)

  • PM-4 412003 PORV/ Code Safety Tailpipe Temperature NUREG-0680 At Plant None (8-2.1.3.a)
  • PM-8A 412065 TSC Computer Operations /CRT/ Intercom NUREG-0680 Installation /

None (8-2.2.2.b)

IWL Items

+ PM-8C 432014 Near Site Emergency Operations Facility NUREG-0746 Engineering N/A (II.H)

+ PM-8D 432014 Environmental Command Center Upgrade NUREG-0746 Engineering N/A (II.H)

None

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(various)

IWL Items

At Plant None

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TMI-l MODIFICATIONS Revision 3 CROSS REFERENCE LISTING May 11, 1982

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(TASK TO REQUIREMENT)

Page 6 of 10 NRC MODIFICATION INSPECTION TASK N0. B/A NO.

DESCRIPTION REQUIREftENT STATUS STATUS o PM-32 412070 Relay Room Catwalk Seismic Upgrade Tech. Specs.

Engineering /

Partially (LER 81-11)

QC Inspection Completed o RM-1 412049 Heat Shrink Tubing / Butt Splicing Inside RB Bulletin Installation Partially 79-01B Completed o RM-3B 412051 Reactor Trip on Loss of Feedwater NUREG-0680 At Plant Partially (79-05B-5)

Completed

  • RM-4A 412056 Connect Incore Thermocouples to Computer NUREG-0680 At Plant Partially (8-2.1.3.b)

Completed o RM-4B 412056 Incore Thermocouple Backup Display System NUREG-0680 Installation None (8-2.1.3.b)

o RM-5B 412052 R.B. Isolation on High Radiation NUREG-0680 At Plant Partially (8-2.1.4)

Completed o RM-SC 412052 R.B. Isolation on Reactor Trip /High R.B.

NUREG-0680 IWL Items Partially Pressure /HPI (8-2.1.4)

Completed o RM-5D 412052 R.B. Isolation on NSCCC and ICCC Pipeline NUREG-0680 IWL Items None Break (8-2.1.4)

s

  • RM 7 412054 Computer Modification-High Speed Printers /CRT NUREG-0752 (2)

IWL Items None o RM-8'

120002'

Raise Steam Generator Level Transmitter PID (IIT, Accepted Partially

.

1 1174)

Completed I

o RM-9 120002 Raise Setpoint of Power Operated Relief Valve NUREG-0680 Accepted Partially (79-05B-3)

Completed

  • RM-10/ 412042 PORV and Safety Valve Position Indication NUREG-0680 Testing /

Partially LM-8C (8-2.1.3.a)

At Plant Completed

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TMI-l MODIFICATIONS Revision 3 CROSS REFERENCE LISTING May 11, 1982

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(TASK TO REQUIREMENT)

Page 7 of 10 NRC MODIFICATION INSPECTION TASK N0.

B/A N0.

DESCRIPTION REQUIREMENT STATUS STATUS

Partially (8-2.1.5.a)

At Plant Completed

  • RM-13A 412012 Backup Instrument Air System NUREG-0680 Accepted Completed (ST la-2)

except Testing

  • RM-13 412012 Emergency Feedwater Auto Start (Control Grade)

NUREG-0680 Accepted Completed A/E (ST la-1, la-3)

None (8-2.1.7.b)

At Plant

  • RM-13C 412012 Emergency Feedwater Control Valves -

NUREG-0680 Accepted Completed

" Fail Open" (ST la-2)

  • RM-13D 412012 Emergency Feedwater (Alternate Manual Controls)

NUREG-0680 (lb)

Accepted Completed

  • RM-13 412012 Emergency Feedwater Auto Start (Safety Grade)

NUREG-0680 Accepted Completed E/A (8-2.1.7.a)

except Testing

except Testing

  • RM-13H 412012 EFW Pump Turbine Safety Valves Lift Setpoints NUREG-0680 Accepted Completed (la-Add'l 6)
  • RM-13H 412012 Two Hour Backup Air Supply NUREG-0680 Installation /

None (la-Add'l 6)

Accepted I

  • RM-13I 412012 Condensate Storage Tank Low-Low Level Alarm NUREG-0680 Testing Partially (la-Add'l 1)

Completed

+ RM-131 412012 CST Low Level Alarm-Independent Power NUREG-0680 Engineering N/A Supplies (8-2.1.7.a)

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O TMI-l MODIFICATIONS Revision 3

'

CROSS REFERENCE LISTING May 11, 1982

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(TASK TO REQUIREMENT)

Page 8 of 10 NRC MODIFICATION INSPECTION TASK NO.

B/A NO.

DESCRIPTION REQUIREMENT STATUS STATUS

  • RM-13J/ 41E012 OTSG Level in C.R. Independent of ICS NUREG-0680 IWL Items None LM-38 (8-2.1.7.a)

> * RM-14 412072 High Pressure Injection Cross Connect PID (110, Accepted Partially

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5 943)

Completed

  • RM-16 412063 Pressurizer Heater Emergency Pcwer NUREG-0680 IWL Items Partially (8-2.1.1)

Completed

  • RM-17 412029 Power Supply to ICS/NNI System NUREG-0680 Accepted Partially (LT-1)

Completed

  • RM-21 412061 Relocation of Radiation Monitors NUREG-0680 IWL Items /

None (8-2.1.8.b)

At Plant

  • TS-147 220010 Independent TMI-2 Sampling System NUREG-0680 (4)

Accepted None

  • WG-56 432061 Low Level Solid Waste Storage Facility NUREG-0680 (5)

Installation None

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120011 Steam Generator Long Term Tube Repairs Tech. Specs.

Engineering None

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(LER 81-13)

>

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120012 Steam Generator Tube Plugging Tech. Specs.

Engineering /

None (LER81-13)

QC Inspection

  • --

120016 Primary System Review Tech. Specs.

Engineering None (LER 81-13)

  • --

412019 Pressure Temperature Plot Part-Task Trainer PID (IIM, Accepted Completed Condition 4)

+ --

412006 Replicate Simulator PID (IIM, Engineering N/A Condition 5)

+ --

412019 Basic Principles Trainer PID (IIM, Engineering N/A Condition 6)

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TMI-l MODIFICATIONS Revision 3 CROSS REFERENCE LISTING May 11, 1982

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(TASK TO REQUIREMENT)

Page 9 of 10 NRC MODIFICATION INSPECTION TASK NO.

B/A NO.

DESCRIPTION REQUIREMENT STATUS STATUS

+ --

412023 Reactor Vessel Water Level Instrument NUREG-0680 Engineering N/A (8-2.1.3.b)

+ --

412031 EFW Control Valves-Environmental Qualification NUREG-0680 Engineering N/A (la-Add'l 7)

  1. --

412031 Material Qualification Replacement Items PID (IIT, Engineering N/A 1 1163)

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412088 Overpressure Protection at Low RC Temperatrue TSA No. 56/

Engineering None TSCR No. 74

  • --

412068 Control Room Habitability Upgrade TAP III.D.3.4 Engineering None

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412244 Remote Shutdown Capability Appendix R Engineering N/A

  • --

412250 Control Room Lighting & Glare Reduction NUREG-0752 Installation None

  • --

412251 Alarm System Reformat NUREG-0752 Installation None

+ --

432107 Protected Area Barrier Intruder Det. Sys.

Proposed Security Engineering N/A Plan Rev.

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TMI-l MODIFICATIONS Revision 3 I

CROSS REFERENCE LISTING May 11, 1982

.

(TASK TO REQUIREMENT)

Page 10 of 10 EXPLANATION OF MODIFICATION STATUS SYMBOLS AND CATEGORIES Task Requirement Status Symbols:

Task scheduled for pre-rectart installation.

  • Task scheduled for post-restart installation.

+

Task pending NRR review of proposed design /SBLOCA analysis.

New Task / Engineering not issued.

l Modification Status Categories:

Engineering - Modification in aNroval process (funding / engineering design / Quality Centrol (QC) hold and witness review / safety evaluation review / work package planning)

Installation - Work package released for installation by Maintenance and Construction (M&C), Plant Maintenance, or Startup and Test organizations QC Inspection - Completed modification installation package to M&C Planning for release to QC/Startup and Test or package at QC for inspections Test / Testing - Work package at Startup and Test / Plant Engineering for testing, or M&C to provide final as installed drawing package IWL Items - Modification package includes incomplete work list (IWL) items preventing release to plant staff for I

acceptance i

l At Plant - Modification package at plant for acceptance review or package in final turnover signoff process Accepted - Modification package accepted by plant NOTE:

Summary and detailed modification status for the above tasks with regards to engineering, production (installation) planning and schedulino, production installation in progress, QC certification, modification testing, and plant acceptance is contained in the following licensee documents:

(1) TMI-l Restart Modifications Status Report.

(2) TMI-l M&C Schedule - Modifications in Production.

(3) TMI-l Pestart Project Status Meeting Agenda.

q J

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