IR 05000289/1980001
| ML19312D935 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/28/1980 |
| From: | Conte R, Haverkamp H, Plumlee K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19312D934 | List: |
| References | |
| 50-289-80-01, 50-289-80-1, 50-320-80-01, 50-320-80-1, NUDOCS 8005220768 | |
| Download: ML19312D935 (13) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF IflSPECTION AND ENFORCEMENT
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Region I 50-289/80-01 Report No.
50-320/80-01 50-289 Docket No.
50-320 DPR-50 c
License No. DPR-73 Priority Category c
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Licensee:
Metropolitan Edison Company 100 Interpace Parkway Parsippany, New Jersey 07054
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Facility Name:
Three Mile Island Nuclear Station Units 1 and 2 Inspection at: Middletown, Pennsylvania
Inspection conducted:
January 5 - January 31, 1980 Inspectors:
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D.R.Haverkamp,SefiorResidentInspector date signed CM s/u /w R. Jt-Conte, Senior Resident Inspector date signed
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'K! E. Pluml e, Senior Radiation Specialist date signed Approved by: N //
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A. N. F4sano, Chief, Site Operations Section, d6te sfigned l
NRC/TMI Technical Support Staff Inspection Sumary:
Inspection on January 5-31, 1980 (Combined Report Nos. 50-289/80-01; 50-320/80-01).
Areas Inspected: Special inspection by HRC/TMI Technical Support Staff of licensee action on previous inspection findings (Units 1 and 2); new and revised procedures (Unit 2); plant operations including shift activities as monitored by NRC shift inspectors (Units 1 and 2); casualty drills (Unit 2); and contaminated TLD's (Unit 2).
The inspection included day shift coverage with selected back-shift coverage by NRC shift radiation specialists.
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Results: No items of noncompliance were. identified.
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8005220768
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DETAILS 1.
Persons Contacted Licensee Representatives Principal licensee and contractor personnel contacted during this inspection are identified in paragraph 8.
NRC Inspection Participants The following personnel participated in this inspection.
G. Belisle, IE:RII, January 5 - January 9,1980 J. Bland, IE:HQ, January 23 - January 31, 1980 M. Campbell, IE:RI, January 9 - January 16, 1980 R. Conte, IE:RI, January 5 - January 31, 1980 i
J. Davis, IE:RII, January 16 - January 23, 1980 S. Ewald, IE:RII, January 5 - January 9,1980 A. Fasano, IE:RI, January 28 - January 31, 1980 E. Ford, IE:RII, January 30 - January 31, 1980 D. Haverkamp, IE:RI, January 5 - January 31, 1980 A. Horn, IE:RV, January 16 - January 31, 1980 l
G. Kalman, IE:RI, January 5 - January 31, 1980 J. Kinneman, IE:RI, January 16 - January 30, 1980 T. Martin, IE:RI, January 5 - January 28, 1980 W. Millsap, IE:RII, January 30 - January 31, 1980
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R. Nimitz, IE:RI, January 30 - January 31, 1980 K. Plumlee, IE:RI, January 5 - January 31, 1980 J. Puckett, IE:RII, January 23 - January 30, 1980 J. Serabian, IE:RI, January 9 - January 23, 1980 G. Troup, IE:RII, January 5 - January 9, 1980
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J. Wray, IE:RII, January 9 - January 16, 1980 2.
Licensee Action on Previous Inspection Findings (Closed) Noncompliance 289/79-03-01:
Failure to wear the pro-
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tective clothing specified on a radiation work permit.
Licensee auditing and enforcement of protective clothing requirements were reviewed. The conduct of work was observed on various shifts.
Licensee corrective actions, as described in Met-Ed letter to NRC Region I, serial GQL 1126, dated August 29, 1979, were completed satisfactorily. These measures appeared adequate to correct the item of noncompliance and to prevent recurrence.
The inspector had no further questions concerning this matter.
(Closed) Noncompliance 289/78-06-01:
Inadequate survey for work performed in the Unit 1 steam generators during March 1978.
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Licensee response to this item of noncompliance is contained in l
Met-Ed letters to NRC Region I serial GQL 2047, dated December 22, 1978; serial GQL 0204, dated February 8,1979; serial GQL 1510, dated
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December 11, 1979; and, serial TLL 025 dated January 18, 1980.
NRC l
replies to these letters, including certain refuted matters, are
described in NRC Region I letters to Met-Ed dated May 11, 1978;
July 31, 1978; November 21, 1978; January 29, 1979; November 15, 1979; l
and March 7, 1980. Subsequent extremity dosimetry on five individuals l
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entering steam generators during February 1979, gave as high as a 4.6:1 ratio of extremity dose to whole body dose compared to a maxiumum 2:1 ratio expected by the licensee.
Review of the 1979 records was delayed for several months because of a computer programming problem involving extremity dose information.
Review on October 8,1979, showed that zero extremity doses had been shown in the termination letters, dated April 26, 1979, to four of the above five individuals.
Review on January 31, 1980, showed that corrected termination letters were provided. 'The Unit 1 Radiation Protection Plan and the extremity dosimetry practices have been improved in this area. No personnel overexposures were identified and there were no further questions concerning tr.is matter.
(Closed) Noncompliance 320/79-04-02:
Inadequate radiation monitoring in high neutron radiation areas.
Licensee corrective action included administrative controls to preclude any further entries into high
' neutron radiation areas and engineering efforts to improve the neutron shield.
Biological shielding will be routinely checked by the licensee as appropriate.
Licensee corrective actions, as described in Met-Ed letter to NRC Region I, serial GQL 1126, dated August 29, 1979, were completed satisfactorily and appeared adequate to prevent recurrence. The inspector had no further questions concerning this matter.
3.
Facility Procedures Suomitted for Approval (Unit 2)
Facility procedures and subsequent revisions, required to be sub-mitted for approval to the NRC as required by Technical Specification (TS) 6.8.2, were reviewed by the NRC/TMI Technical Support Staff.
These procedures address the Recovery OperatN:n Plan Implementation
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(Surveillance Procedures) and Recovery Mode Implementation (Operating
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Procedures).
Detailed review of selected procedures included both health physics and operations aspects with consideration of the following:
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the procedure, when implemented, would not degrade tha containment of radioactive material, jeopardize corc cooling, or result in excessive personnel exposure; (2) tb procedure conforms to the general criteria of TS 6.8, " Procedures," TS 6.11,
" Radiation Protection Program," and, ANSI N-18.7,1976; and, (3)
the technical content of the procedure is adequate to perform the intended evolution.
Composite staff comments on procedures were forwarded to the licensee.
No instances of failure to adequately resolve these comments Wre identified.
4.
Review of Plant Operations (Units 1 and 2)
a.
Units 1 and 2 (1) Shift Logs and Operating Records The following logs and records were reviewed.
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Shift Foreman Log and Control Room Operator Log
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Books from November 1978 through January 16, 1979.
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Control Room Operator's Log Sheets, Primary Auxiliary
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Operator's Log-Tour Readings, Primary Auxiliary Operator's Log-Liquid Waste Disposal Panels, Secondary Auxiliary Operator's Log Sheets, and Auxiliary Operations Log Sheets-Out-Building Tour from January 4-16, 1980.
Shift and Daily checks from January 4-16, 1980;
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Jumper, Lifted Lead, and Mechanical Modifications
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Log (active and cleared) from November 1979 through January 16, 1980;
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Fire System Removal from Service Notification Log from November 1979 through January 16, 1980; ISI Tag Book from November 1979 through January 16, 1980,
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(Unit 1 only);
Do Not Operate and Caution Tag Log from November 1979
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through January 16, 1980; Transient Cycle Log Book from November 1979 through
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January 16, 1980; and, Unit 1 Operations Departmant Memo 79-2.
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The logs and records were reviewed to verify the following items:
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Logkeeping practices and log book reviews are conducted in accordance with established adminis-trative controls; Log entries involving abnormal conditions are
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sufficiently detailed; Operating orders do not conflict with Technical
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Specifications (TS);
Jumper log and tagging log entries do not conflict
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with TS; and, Jumper, Lifted Lead and Mechanical modification and
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tagging operations are conducted in conformance with established administrative control.
Acceptance criteria for the above review included applicable Technical Specifications, and the following procedures:
Administrative Procedure (AP) 1002, " Rules for the
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Protection of Employees Working on Electrical and Mechanical Apparatus;"
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AP 1010, " Technical Specification Surveillance
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Program;"
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AP 1012, " Shift Relief and 1.og Entries;"
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AP 1013, " Bypass of Safety Functions and Jumper
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Control ;"
AP 1016, " Operations Surveillance Program;"
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AP 1033, " Operating Memos and Standing Orders;"
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AP 1037, " Control of Caution and DN0 Tags;" and,
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Operating Procedure (0P) 1104-45, " Fire Protection
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System."
No items of noncompliance were identified.
(2) Plant Tour At various times between January 4 and January 16, 1980, tours were conducted of the following accessible Unit 1 and Unit 2 areas:
auxiliary building; turbine building; control and service building; control room; switchgear rooms; and, inverter and battery rooms.
The following observations / discussions / determinations
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were made:
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Control room recorders and monitoring instrunioniation for various process parameters were observed; Radiation controls established by the licensee,
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including the posting of radiation and high radiation areas, the condition of step-off pads, and the disposal of protective clothing, were observed.
Radiation Work Permits used for entry to radiation and controlled areas were reviewed. Actual radiation levels were measured and compared with posted values throughout the plant; Plant housekeeping, including general cleanliness
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conditions and storage of materials and components to prevent safety and fire hazards, were observed; Systems and equipment in all areas toured were
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observed for the existence of fluid leaks and abnormal piping vibrations; Selected piping snubbers / restraints were observed
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for proper fluid level and condition / proper hanger settings;
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The indicated positions of selected electrical power
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supply breakers, control board equipment start switches and remote-operated valves and the actual positions of selected manual-operated valves were observed; Selected safety-related instruments / gauges were
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observed for proper calibration interval; Selected equipment lockout tags, caution tags, and
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do-not-operate tags were observed for proper posting and the tagged equipment was observed for proper positioning, where applicable; Selected jumper and lifted lead markers were observed
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for proper identification and the affected wiring changes were observed for proper completion;
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The Control Board was observed for annunciators that-
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normally should not be lighted during the existing plant conditions. The reasons for the annunciators were discussed with the control room operator;
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Control Room manning was observed on several occasions
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during the inspection, and a shift turnover was observed to verify that continuity of system status was maintained;
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Selected fire extinguishers were observed for unobstructed access and adequate pressure and/or level; Selected fire alarm reporting stations were observed
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to verify that the stations were clearly identified and unobstructed; Battery Room ' ventilation system was observed for
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proper operation; Selected areas were observed to verify that designated
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"no smcking" areas did not exhibit evidence of smoking; and,
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Battery power supplies for selected emergency fire
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protection and lighting equipment were observed for proper operability.
Acceptance criteria for the above items included recuire-ments of 10 CFR 50.54(k), Regulatory Guide 1.114, applicable Technical Specifications, and the following procedures:
AP 1002, " Rules for the Protection of Employees
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Working on Electrical and Mechanical Apparatus;"
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AP 1003, " Radiation Protection Manual;
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AP 1008, " Good Housekeeping;"
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AP 1009, " Station Organization and Chain of Command;"
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AP 1028, " Operator at the Controls;"
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AP 1037, " Control of Caution and DN0 Tags;" and,
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AP 1050, " Control of High Radiation Areas."
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No items of noncompliance were identified.
b.
Unit 1 Status Meetings NRC/TMI Technical Support Staff members attended licensee meetings to observe and ascertain additional plant status information. The meetings attended included those listed below, and involved discussions of:
plant status; specific system operation; pending or planned maintenance and con-struction activities; radioactive waste management and plant radiological status and Restart actions status.
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Unit 1 Plan of the Day / Maintenance Review
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Unit 1 Restart Management Review c.
Unit 2 Status Meetings NRC/TMI Technical Support Staff members attended licensee meetings to observe and ascertain additional plant status information. The meetings attended included those listed below, and involved discussions of:
plant status, specific
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system operation; pending or planned construction activities; radioactive waste management and plant radiological status.
Daily Plant Status Meetings
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Mini-Decay Heat Removal Meetings Weekly Planning Meeting
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Monthly Technical Meeting
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Biweekly Containment Purge Task Force Group Meeting
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Biweekly Containment Entrance Task Force Group Meeting
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No items of noncompliance were identifie '
5.
Shift Inspection Reviews (Units 1 and 2)
a.
Plant Tours On a daily basis NRC shift radiation specialists completed a general plant tour including all control points and selected radiologically controlled areas.
Observations included:
Cleanliness and housekeeping conditions;
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Fire protection measures;
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Construction status and startup testing progress;
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Access control to radiologically controlled areas; o
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Use of survey meters including personnel frisking techniques;
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Proper use of respiratory protection equipment;
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Adherence to Radiation Work Permit (RWP) requirements;
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Various logs / records to ascertain current licensee
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actions / evaluations / problem areas; Adherence to Health Physics and Operating Procedures;
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EPICOR I and II operations;
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Waste solidification and shipping; and,
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Dry wasto compacting.
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b.
Iieasurement Verifications The below listed measurements were independently obtained to verify the quality of licensee performance in these selected
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areas:
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Radioactive Material Shipping; and, Radiological Control Radiation and Contamination Surveys.
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No items of noncompliance were identified during shift inspection reviews.
6.
Casualty Drill Observations (Unit 2)
Casualty drills involving Unit 2 personnel were observed by a.
the NRC/TMI Technical Support Staff to verify the following:
Organizational response was coordinated, orderly and
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timely;
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Immediate and supplemental actions of the applicable
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emergency procedures were properly implemented; Adequacy of health physics practices, radiological dose
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assessment and utilization of emergency response kits for radiological emergencies; Adequacy of internal communication systems and techniques;
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Licensee use of " drill observers" to evaluate " drill
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participant" response, and the adequacy of drill observer comments; and, Corrective actions were initiated by the licensee to
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correct identified deficiencies.
b.
The'following documents were used by NRC/TMI staff as references in the preparation for and observation of these casualty drills:
i Selected sections of the Three liile Island Emergency
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Plans and Procedures Volumes I and II (Administrative Procedure 1004, Revision 12, April 21,1979);
Station Radiation Emergency Procedure (SREP) 1670.1,
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Local Emergency Procedure, Revision 6, February 13, 1978; SREP 1670.2, Site Emergency Procedure, Revision 9,
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Nove:r.ber 27, 1978; i
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Unit #2 Emergency Procedure (EP) 2202-4.10, Dropped
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Prefilter/ Liner Outside of the-Chemical Cleaning Building; EP 2202-4.13, Rupture or Leak in a Reactor Coolant Bleed
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Tank, Revision 0, November 29, 1979; EP 2202-3.1, Fire, Revision 4, October 6,1978; and,
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Licensee prepared Scenarios for the drills listed below.
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The following casualty drills were observed:
Reactor Coolant Bleed Tank Rupture on January 16, 1980;
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Makeup Valve Packing Blowout on January 17, 1980;
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Dropped EPICOR II Demineralizer Liner on January 18, 1980;
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Fire in Radwaste Storage Area on January 23, 1980;
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Failed Open Reactor Building Purge Valve on January 24, 1980;
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DH-V6B uross Packing Leak on January 25, 1980; and,
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Dropped EPICOR II Demineralizer Liner on January 28, 1980.
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In addition, licensee conducted drill critiques were observed
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for each drill.
Comparisons were made between licensee
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observer comments and NRC/TMI staff comments.
Additional NRC coments were given to the licensee / drill observers as feed-back on certain drills.
During the drill periods improvement was noted in the quality of licensee observer coments.
d.
The findings noted below summarize the major deficiencies identified during the conduct of the casualty drills.
Material Problems Vehicles for onsite and offsite monitoring teams need to
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be designated and adequately equipped for emergency use; There is a shortage of properly designated radios (i.e.,
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channels marked for emergency use) in the licensee's communications network; Emergency response kits are needed in Unit 2 especially
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at the EPICOR II area; The public address system was inaudible (" blind spots")
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in certain locations of the plant (e.g., EPICOR II outside area between the borated water storage tank and chemical cleaning building);
NRC Bulletin No. 79-18, Audibility Problems Encountered on Evacuatics of Personnel from High Noise Areas, will be addressed by the 1;censee for the entire site; and, Remote fire / radiation alarm capability was needed at the
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radwaste storage area.
Personnel Problems
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Qualifications of individuals manning responsible positions need to be delineated in the Emergency Plan.
Further review is neec'ed to assure that managers of the response organization nave time to think and are not assigned mundane tasks; Emergency Control Center (ECC) needs administrative aides
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to assist in what has to be done, which actions were initiated, what actions were accomplished with feed-back/results (e.g., checklist of action and status board list of orders issued);
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Dose assessment needs " quick" calculation procedures for source tenns and they need training in those procedures; The Emergency Plan needs to address when an emergency
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dose will be taken and who will make that decision;
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Response team members need to become familiar with the
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use of Emergency Response Kits and radio communication equipment; N
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The method of dispatching radiation monitor teams needs
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to return to the group concept.
Toward the end of,the drill period personnel were dispersing rather than working as a team; Not all personnel approached radiation problems with
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instruments for dose rate information; and, Some personnel failed to recognize the need for air
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sample monitor filter changeout when effluent monitors were off-scale.
(Further on'one instance counting of air
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samples was performed in high background areas.)
The licensee representative acknowledged the above findings sand stated that corrective action was initiated to correct the material problems identified above.
Further it was agreed that additional personnel training was needed to solve me e of the personnel problems noted above.
Further, the licensee representative agreed to conduct quarterly drills in light of the radiological situation in Unit 2 due to the March 28 accident.
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The correction of the above findings is unresolved pending completion of action by the licensee and subsequent review by NRC/TMI staff (320/80-01-01).
7.
Contaminated personnel TLD Dosimeters
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An attempt to use 50 previously exposed personnel TLD dosimeters to take supplemc:ntal environmental dose rate measurements, from November 1 to November 30, 1979, resulted #n the discovery that at least 10 of the 50 were contaminated with Cesium -134 and -137.
The. regularly posted environmental dosimeters were not affected.
The licensee's review of the information resulted in a decision to count and analyze, first a few, and finally, all of the set.
Five detectably contaminated TLD cards were identified on December 21, 1979,
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and five more on January 22, 1980.
Corrections will be made to the dosimetry records of any individual whose record is shown to be significantly in error because of wearing a contaminated TLD badge. The most contaminated TLD card
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was measured at 11,011 dpm Cs-137 and 3,685 dpm Cs-134.
This resulted in an estimated 610 mrem greater dose than was usual at the place where it was posted, during November 1 to 30,1979.
The contaminated badges were removed from use.
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The licensee will provide a final internal report on this item.
This report will be reviewed on a subsequent inspection (320/80-01-02).
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Exit Interviews Meetings were held with licensee management to discuss inspection findings and concerns as noted below.
Unit 1 Meeting on February 5, 1980 Licensee Representatives R. Harbin, Assistant to the Manager, Unit 1 W. Potts, Manager-Radiological Controls NRC Representatives A. Fasano, Chief, Site Operations Section
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D. Haverkamp, Unit 1 Senior Resident Intuector M. Shanbaky, Senior Radiation Specialist
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Summary of findings in the operations and health physics areas were discussed.
Unit 2 Meeting on January 21, 1980
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Licensee Representatives J. Barton, Manager Site Operations, Unit 2 D. Ferguson, NSS Radcon Field Operator
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R. Heward, Manager Radiological Controls G. Kunder, Supervisor Technical Specification Compliance B. Smith, Shift Supervisor NRC Representatives
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R. Conte, Unit 2 Senior Resident Inspector T. Martin, Acting Chief, Site Operations Section K. Plumlee, Acting Senior Radiation Specialist
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J. Serabian, Shift Radiation Specialist l
Summary of findings for.the first three casualty drills were discussed.
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Unit 2 Meeting on January 31, 1980 Licensee Representatives J. Barton, Mccager Site Operations, Unit 2
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R. Heward, Manager Radiological Controls G. Kunder, Supervisor Technical Specification Compliance i
J. Renshaw, Supervisor Health Physics Operations l
P. Ruhter, Manager Radiological Technical Cupport l
B. Smith, Shift Supervisor
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NRC R!pr:sentatives
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R. Conte, Unit 2 Senior Resident Inspector A. Fasano, Chief Operations Section K. Plumlee, Acting Senior Radiation Specialist M. Shanbaky, Senior Radiation Specialist Summary of findings in the operations and health physics areas (emergency preparedness) were discussed.
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