IR 05000289/1980019
| ML19340B444 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/25/1980 |
| From: | Allenspach F, Crocker L, Haverkamp D, Keimig R, Norrholm L, Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19340B443 | List: |
| References | |
| 50-289-80-19-01, 50-289-80-19-1, NUDOCS 8011100531 | |
| Download: ML19340B444 (14) | |
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O U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-289/80-19 Docket No. 50-289 Priority Category C
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Licensee-Metropolitan Edison Comcany ATTN: Mr. R. C. Arnold Senior Vice President 100 Intercace Parkway Parsiopany, New Jersey 07054 Facility Name:
Three Mile Island - Unit 1 Itspection at:
Middletown, Pennsylvania and GPU Corporate offices in Parsippany, New Jersey Inspection conducted: July 23-25, 1980
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Inspectors:
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.R.Keifi,If 6 ate f gned jf L. J. Norruolm, SNGS-N)tC d' ate signed
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Residen Inspector (Ah k
9/zf/PC 0. R. HaverKamp, TMIfl NRC date signed Resi en gpectord A
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- F. R. All s ac g DHFS cate figned drk 94f/6
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. P. Cr er, N
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Other Accompanying Personnel:
_E J. Brunner, IE:RI date signed H. Silver, NRR:0L cate signed N24/RO
~h Approved by:
E. A. Brunner, Chief, Reactor date signed Operations and Nuclear Support Branch Inspection Summary:
Inspection on July 23-25, 1980 (Inspection Report No. 50-289/80-19)
Areas Insaetted:
Special, announced NT0L type inspection (132 hours0.00153 days <br />0.0367 hours <br />2.18254e-4 weeks <br />5.0226e-5 months <br />) by an NRC:NRR/li Teu (6 persons) of utility management and technical competence in the areas of:
shift technical advisors; staffing for startup testirig program; on-site technical support center; on-site operational support center; independent safety reviews; off-site and on-site staffing; dissemination of operating experiences; and, communications with NRC.
Results:
No items of noncompliance or deviation were identifie. _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _.
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DETAILS
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1.
Persons Contacted
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R. Barley, Lead Mechanical Engineer l
- P. Clark, Office of the President (GPUNC)
- J. Colitz, Manager, Plant Engineering l
S. Crouch, STA Instructor (NUS)
G. Giangi, Emergency Plan Coordinator a
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- R. Goodwin, Emergency Planning Consultant (EI)
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- L. Harding, Supervisor of Licensing, Unit 1
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- J. Herbein, Vice President, Nuclear Operations
- H.
Hukill, Director, THI-1 l
C. Irizzary, Career Development Supervisor N. Kazanas, Manager, Quality Assurance i
- R. Keaton, Manager, System Engineering
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R. Long, Director, Nuclear Assurance
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G. Miller, Manager Restart Startup Test Program M. Moore, STA Training Coordinator R. Neil, Manager, THI-1 T aining M. Nelson, Safety Review Manager i
V. Orlandi, Lead IC Engineer G. Reed, Supervisor, Chemistry M. Ross, Supervisor, Operations
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D. Shovlin, Supervisor, Maintenance J. Thorpe, Chairman, TMI General Office Review Board R. Toole, Manager, Unit 1
- E. Wallace, Licensing Manager S. Wilkerson, Lead Nuclear Engineer R. Wilson, Director, Technical Functions
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- Present at Exit Interview on July 25, 1980.
2.
Purcose of Inspection
The purpose of this inspection was to assess the status of compliance by Metropolitan Edison Company (and/or GPU Nuclear
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Group), holder of NRC License No. DPR-50 for the operation i
of Three Mile Island Nuclear Station, Unit 1, with the NRC's
" Criteria for Utility Management and Technical Competence".
The inspection included the general areas of on-site and off-site staff organization and technical resources.
3.
L_icensee Action on Previous Inspection Findings Not inspecte.
4.
Reference Documents The following documents were reviewed and used for reference purposes in the preparation for and the conduct of this inspection, as applicable.
Other documents, applicable to specific areas inspected, and used for review and reference purposes, are listed in the paragraph which addresses that area.
a.
NUREG-0578, TMI Lessons Learned Task Force Status Report and Short Term Lessons Learned, dated July 1979.
b.
NUREG-0680, TMI-1 Restart, dated June 1980.
c.
TMI-1 Restart Report (and amendments thru No. 20)
d.
Draft Criteria for Utility Management and Technical Competence, dated July 1980.
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e.
U.S. NRC Regulatory Guide 1.8, " Personnel Selection and Training", Revision 1, September 1975.
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ANS 3.1, Draft Revision, dated December 1979, " Standard for Qualification and Training of Personnel for Nuclear Power Plants".
5.
Independent Safety Review Function The objective of this portion of the inspection was to determine whether the licensee has established or plans to establish an onsite safety engineering group to perform independent reviews of plant operational activities and engineering evaluation of the operating history of the plant and plants of similar design.
Findings, The licensee has two functional review committees as required by facility Technical Specifications:
the General Office Review Board (GORB) and the Plant Operations Review Committee (PORC).
Both committees are dedicated to Three Mile Island Unit 1.
PORC members are exclusively Unit I staff.
Some members of GORB serve on committees for other nuclear units within the holding company's system.
The PORC chairman is the Safety Review Manager, who reports on-site to the Director, TMI-1.
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A dedicated full-time safety review group was being established at the tire of the inspection.
The licensee stated that a functional description of the group and its composition will be included in a revision to the TMI-1 Restart Report which is expected to be submitted to NRC by August 8, 1980, and documented in subsequent change request to the Unit 1 Technical Specifi-cations.
The change request will also indicate that the Safety Review Manager will report off-site to the Manager-Nuclear Safety Assessment. The responsibilities of the Independent On-Site Safety Review Committee (IOSRC)
are expected to include independent reviews of operational activities.
The following aspects of the IOSRC will be reviewed during a subsequent inspection pending approval of the proposed change:
qualifications of members; review procedures and charter; and, independence from operating organization.
This is an open item (50-289/80-19-01).
6.
Onsite Technical Support Center (TSC) and Onsite Operational Support Center (OSC)
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The objective of this portion of the inspection was to determine whether the licensee has established an onsite technical support center (TSC) and an onsite operational support center (OSC) to accommodate technical and operational personnel support responding to an emergency situation.
a.
Docuraents Reviewed (1) GPU Nuclear Corporation Emergency Plan for Three Mile Island Unit 1, Revision 2, dated June, 1980.
(2) EPIP 1004.28, Activation of the Technical Support Center (Draft).
(3) EPIP 1004.29, Activation of the Operational Support Center (Draft).
(4) TMI-1, Onsite Emergency Outy Roster (typical)
b.
Findings The inspection of this area included the inspector's verification of action taken by the licensee with regard to commitments made in applic-able documents.
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The licensee has established a TSC located in the Remote Shutdown Station area below the Control Room on elevation 322'.
A display unit and patch board provide approximately 100 plant parameters through the use of instrument signal voltage readings and conversion data.
Space for reference material and 25 support personnel is available.
Portable radiation monitoring equipment is in place,as well as communication links to NRC and the control room. A duty section schedule is in use which assigns engineering support personnel who will report to the TSC, when activated.
The licensee has also established an OSC at the Health Physics Access Control Point on elevation 306' in the Control Building.
This will serve as the muster station for operations and support personnel in the event of an emergency.
Adequate communications have been provided.
An OSC Coordinator is assigned via a duty section schedule.
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As detailed in the June 1980 proposed Emergency Plan, the Emergency Director and Radiological Assessment Coordinator will be stationed in the control roem area.
The TSC will provide only engineering technical support.
These aspects, as well as others of the Emergency Plan, currently are under review by other members of the NRC staff.
The following items apply to implementation of the actions identified in the referenced documents and are identified as open pending further review during subsequent inspection:
Reference material such as as-built drawings, and other
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technical documents have not been placed in the TSC, as yet. The licensee stated that the reference material would be in place by April 1,1981.
(289/80-19-02)
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Dedicated telephone communications between the TSC and the licensee's corporate headquarters have not been installed. The licensee stated that installation would be complete by April 1, 1981.
(289/80-19-03)
Emergency Plan implementing instructions describing
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the operation, activation, and roles of the TSC and OSC have been drafted but have not been formally approved and issued, to date.
The licensee stated that these precedures would be issued by September 7, 1980.
(289/80-19-04)
No items of noncompliance or deviation were identifiec.
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6.
Shift Technical Advisor The objective of this portion of the inspection was to determine the licensee's plans to provide a technical advisor to the shift supervisor on all shifts and to assess the training program established or planned for theta advisors.
a.
Additional Documents Reviewed TMI Training Manual, Section 6.1 b.
Findings There are two full time individuals in charge of administering the overall training effort at TMI-1. The individual in charge of the site program has a PhD in Nuclear Physics.
The on-site training staff has about 46 full time members.
The formal training program for the Shift Technical Advisor (STA)
was. examined. The program is described in the TMI Training Manual Section 6.1.
This program consists of a ncminal two year combined classrecm and on-shift practical course.
Selected STA written tests and completed examinations were reviewed for technical content.
The examinations were found to be highly technical and detailed. The procedures for developing the examinations and answer keys were discussed with training staff personnel and found to provide inputs from both the technical functions and operational staffs.
The detailed schedule for completion of an accelerated training course for the first eight STA candidates was examined.
No STAS will be fully trained prior to January, 1981.
Based upon the foregoing, the STA training program appears to meet the requirements specified in the Draft Revision of ANS 3.1. Satisfactory completion of the STA training program by the first group of candidates will be determined during a subsequent inspection.
This item is open.
(289/80-19-05)
No items of noncompliance or deviation were identifie l
7.
Augmentation of Plant Staff for Startup Test Program The purpose of this portion of the inspection was to determine the degree of augmentation and assistance to be given the plant staff for the preoperational and startup test program, including special testing.
Additional Documcnts Reviewed TMI-1, Administrative Procedure 1047, "Startup and Test Manual",
Revision 0, dated March 24, 1980.
Findings Qualified test engineers will be assigned to shift coverage during startup tests of certain modified systems.
Review of personnel qualifications for the test engineering staff, as well as review of the proposed Test Instruction 10, " Training and Qualifications of Test Personnel", are identified as open pending review during subsequent inspections prior to commencement of this activity.
(50-289/80-19-06)
In addition to the aforementioned test engineers, additional shift coverage during testing is planned to be provided by NSSS personnel for the special startup tests and through the power ascension test program.
It was noted that all startup test procedures, changes to the procedures, and test results will be reviewed by a Test Working Group (TWG). The TVG Will consist of one (1) member and at least one (1) alternate from the following organizations:
(1) * Startup and Test (Chairman)
(2) * Plant Supervisory Staff (3) * NSS Supplier (4) * Architect Engineer (5) ** Site Quality Assurance Mod /Op (6) GPU Plant Analysis
- Voting member
- Voting member for important-to-safety testing only The majority of operating staff also possesses experience gained from the original Three Mile Island Unit 1 startup test program and from previous plant operatio. _ _
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Routine IE Inspections conducted prior to and during the testing phases will determine the adequacy of the licensee's test program implementation.
No items of noncompliance or deviation were identified.
8.
Offsite Staff Organization and Technical Competency The objective of this part of the inspection was to review the organization and the management and technical capabilities of the utility's offsite staff.
In performing this task, the utility corporate organizational structure and the responsibilities and qualifications of the principal corporate officers who deal with the utility's nuclear plants were reviewed.
The interface arrangements between the corporate officials and the TMI-1 plant staff and the means by which corporate management stays informed about the TMI-l plant status and involved in matters pertaining to plant safety were also examined.
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Discussion of Offsite Organizational Changes At the time of this inspection, the corporate organization was in the process of being modified such that the nuclear expertise of Metropolitan Edison. company, Jersey Central Power & Light Company and General Public Utilities Service Corporation were being consolidated into one corporate group to support all of the nuclear power plant activities under the cognizance of the General Public Utilities System.
This combined group was referred to as the GPU Nuclear Group (GPUNG).
Upon receipt of the necessary regulatory approvals, the name of the group will change to GPU Nuclear Corporation.
Subsequent to the inspection (on August 8,1980),
the licensee filed Amendment No. 20 to the TMI-1 Restart Report, which documented the intended change to GPU Nu; lear Corporation and the interim designation of the GPUNG.
- The inspection cf this area included interviews with representatives of the licensee during the inspection and information contained in Amendment No. 20 to the TMI-1 Restart Report.
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Findings The corporate organization supporting the TMI-1 plant was evaluated and compared to the NRC staff's guidelines as set forth in the draft Criteria for Utility Management and Technical Competence.
It was found that the GPUNG provides an integrated organizational arrangement for the overall management and technical support of the TMI-1 nuclear power plant operations.
Responsibility for the safe ~ operation of TMI-1 was clearly established and the resources needed to implement this responsiblity appeared to be provided.
The organization provides for unambiguous management control and effective lines of authority and communication between and among the organizational units involved in the management, technical support, and operation of TMI-1.
Measures had been established to perform independent reviews and surveil-lance of plant activities to provide technical support to the plant staff for maintenance, modifications, operational problems, and cperational analysis, and to ensure the implementation of programs at the plant in the areas of quality assurance, physical prote'ction, fire protection, radiation protection, personnel training, and emergency planning.
Based upon the foregoing, it appears that the off-site organization's management and technical capabilities, in support of TMI-1 operations, are acceptable.
An open item was identified milative to the licensee's formal training program for off-site personnel who would be called upon to respond in an emergency.
This training program had not been fully developed and documented at the time of this inspection. The licensee stated that the training program would be available by January 1981.
(289/80-19-07)
No items of noncompliance or daviation were identified.
9.
On-Site Staff Organization and Technical Competence The objective of this part of the inspection was to review the aanagement and technical capability of the TMI-1 nuclear plant staff.
In performing j
this task, the plant staff organizational arrangement, responsibility, authority and qualifications of plant staff principal personnel, shift crew composition, and interfacing of principal personnel with offsite groups supporting the THI-1 plant staff was reviewed.
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4 Discussion of On-Site Organization In conjunction with the Off-Site Staff organization discussed in paragraph 8, and in an effort to strengthen the overall on-site operating staff, significant changes in the site organization and increases in staffing have
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been implemented.
Site operations are the responsibility of the Director, TMI-1 who reports to the Chief Operating Executive, GPUNG (Senior Vice President, Metropolitan Edison Company).
Reporting to the Director, TMI-1 are the following positions: Manager Plant Engineering - responsible for managing the Technical Engineering Staff including the Nuclear Engineering, Mechanical Engineering, Electrical Engineering, Instrument and Control Engineering, Fire Protection Program and Chemistty; Manager of Unit 1 -
responsible for the operation and maintenance of the unit; the Safety Review Manager - full time chairman of the Plant Operations Review Committee; and the Manager Administration and Services -responsible for the administra-tive functional areas of personnel, budget / cost control, security, industrial safety and facilities.-
Additionally, the onsite groups have considerable backup support from the GPUNG.
Findings The On-Si.e Staff Organization for TMI-1 was evaluated and was found to provide a reasonable organizational structure for the operation of a nuclear power plant with provisions for adequate management and technical support from the GPUNG.
Responsibilities for the safe operation and maintenance of the plant appeared to be defined clearly.
Also, measures had been established for on-site staff to perform independent review of safety related matters, to support maintenance and operations groups and to interface with off-site support. The number of personnel comprising the on-site staff also appeared adequate to support an operating nuclear power plant.
The following items were identified as open and will be reviewed during subsequent NRC inspections:
a.
A procedure detailing the conduct of operations for TMI-1 was in preparation.
It was expected that this procedure will contain the licensee's policy on overtime (and overtime restrictions) or, in the interim, that a separate policy document will be issued.
The licensee stated that this policy will be documented by September 15, 1980.
(289/80-19-08)
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1 b.
The licensee was in the process of reviewing provisions for interfacing among the various groups who function to review plant operations.
The licensee stated that these provisions would be included in a Technical Specification change request which was to be submitted by August 8,1980.
(289/80-19-09)
c.
The resumes of plant staff persennel were insufficiently detailed to permit evaluation of specific work experience.
The licensee stated that more detailed resumes would be provided in Section 5 of the TMI-1 Restart Report to be submitted by August 8, 1980.
(289/80-19-10)
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The Training Department Administrative Manual was under development.
The licensee stated that the manual would be complete by February 1981.
(289/80-19-11)
No items of noncompliance or deviation vare identified.
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Dissemination of Ooeratina Experiences The objective of this portion of the inspection was to determine whether the licensee has established a mechanism for evaluating and disseminating operationa-1 experiences from TMI-1 and other nuclear facilities to the plant staff, training department and corporate personnel.
Additional Documents Reviewed a.
Engineering Procedure, EP-013 " Industry /GPUNC Operating Experience Reviews" Draft.
b.
TMI-1 Administrative Procedure, AP 1032, " Dissemination of'Information" dated August 29, 1977, Revision 0.
Findings A draft of Engineering Procedure, EP-013, "Indus try/GPUNC Operating Experience Reviews," which describes tBe procedure to be used for the evaluation and dissemination of operating
experiences at GPUNG plants and at other nuclear plants was reviewed.
This procedure, in conjunction with the TMI-1 Administrative Procedure 1032 is intended to provide for the collection and evaluation of operating experience information, and dissemination of this information to the appropriate parties at TMI-1 and within the corporate structure.
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The licensee stated that EP-013 would be issued by January 1981.
This item is open pending review, during a subsequent NRC inspection, of EP-013 in conjunction with AP 1032.
(289/80-19-12)
No items of noncompliance or deviation were identified.
11.
Dedicated Communications With NRC The purpose of this portion of the inspection was to ensure that dedicated telephone communications between the plant and NRC are in place and operable.
Findings NRC Emergency Notification System (ENS) telephones have been installed at the Three Mile Island site.
These telephones provide direct " hot if ne" communications with the NRC Operations Center in Bethesda, Maryland and are located in the Unit 1 control room, the shift supervisor's offices, and the NRC resident office.
NRC Health Physics Network (HPN) dial telephones are installed in the Unit 1 health physics office, the shift supervisor's office, the Unit 1 Technical Support Center, the near site EOC, and the NRC resident office. Additional extensions of these' dedicated telephone lines are selected for installation, pending final determination of emergency response communication requirements.
No items of noncompliance or deviation were identified.
12.
Unresolved Items No unresolved items were identified during this inspection.
However, twelve items remained open at the conclusion pending actions by the licensee with regard to these matters and the NRC staff's evaluations and findings relative to the adequacy of those actions. These items will be reviewed during subsequent NRC inspections.
(See paragraphs 5, 6, 7, 8, 9, 10).
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Exit Interview The inspectors met with representatives of the licensee (as denoted in paragraph 1) at the conclusion of the inspection on July 25, 1980.
The findings of the inspection were presented and the licensee was requested to provide dates by which actions would be complete on those items identified as open. The licensee requested time to better define the scope of work necessary to complete the items and stated that the dates would be provided in a letter to NRC at a later date. The licensee communicated the completion dates in a letter to NRC Region I, dated August 25, 1980. The completion commitment dates contained in that letter are indicated in this report.
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