IR 05000334/1979014
| ML19254E396 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/23/1979 |
| From: | Baunack W, Blumberg N, Kister H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254E390 | List: |
| References | |
| 50-334-79-14, NUDOCS 7911010030 | |
| Download: ML19254E396 (15) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-334/79-14 Docket No. 50-334 License No. DPR-66 Priority:
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Category:
C Licensee:
Duquesne Light Company 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Facility Name:
Beaver Valley Power Station, Unit No. 1 Inspection at:
Shippingport, Pennsylvania Inspection condu ed:
June 5-8, 1979
'hf Inspectors:
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M N. Blumberg, / Reactor Inspectp date signed RP%k 6'laa hs W. BaungK, Reactor Inspectpr date signed
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A /ha ~
F/o/W r
C. Sweinhart,[nspector Co-Op / (/
date ign d Approved by:
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.33
H. Kistef, ' Chief, Nuclear Support dite si(gned Section 2, RO&NS Branch Inspection Summary:
Inspection on June 5-8, 1979 (Report No. 50-334/79-14)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of licensee action on previous inspection findings; facility procedures for administrative controls; conformance to Technical Speci-fications; temporary and permanent changes in conformance to Technical Speci-fications and licensee procedures; changes in procedures pursuant to 10 CFR 50.59(a)
and (b) requirements; checklists and related forms for currency to latest changes; procedures for administrative control of safety-related maintenance; safety-related maintenance activities; facility tour; and Control Room observations.
The inspection involved 69 inspector-hours onsite by twc regional based NRC inspectors and one inspector co-op.
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Results:
Of the ten areas inspected, no items of noncompliance were identified in seven areas; one item of noncompliance was found in one area (Infraction -
Failure to monitor Reactor Coolant System and Pressurizer heatup and cooldown rates - see Paragraph 6); one item of noncompliance was found in a second area (Deficiency - Failure to properly control temporary changes - see Paragraph 4.c); and one item of noncompliance was found in a third area (Deficiency -
Failure to report a reportable occurrence - see paragraph 10.c).
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DETAILS 1.
Persons Contacted Principal Licensee and Contract Employees,
- R. Balcerek, Maintenance Supervisor
- D. Batina, Quality Assurance Engineer
- J. Carey, Technical Assistant-Nuclear D. Crouch, Shift Supervisor J. Frenn, Maintenance Procedures Engineer
- L. Hutchison, Station Quality Assurance Engineer
- F. Lipchick, Station Quality Assurance Engineer
- E. Kurtz, Senior Quality Assurance Engineer R. Prokopovich, Reactor Engineer
- l Schad, Operations Supervisor J. Turner, Shift Supervisor
- J. Vassello, Training Supervisor
- J. Welch, Westinghouse Instrumentation Service Company (WISCO)
Consultant J. Wenkhouse, Reactor Control Chemist
- J. Werling, Station Superintendent
- H. P. Williams, Chief Engineer The inspectors also interviewed several other licensee employees during the inspection, including reactor operators, technicians, technical support and office personnel.
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed)
Inspector Follow Item (334/78-20-04):
Procedure OST 1.33.13, Fire Protection System Detection Ir.stemnentation Test, required revision to specify correct surveillance frequency.
Inspector review of.tevision 10, May 22, 1979, verified that the proper surveillance frequency is now specified in the procedure.
(Closed)
Inspector Follow Item (334/78-20-08):
Licensee procedures not clear as to when calibration sticker should be used.
BVPS Maintenance Manual, Section 0, Calibration Program, Revision 3, January 10, 1979, now specifies more clearly which plant instruments require calibration stickers.
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(Closed) Unresolved Item 78-20-03:
Procedure titles did not accurately reflect procedure contents, and Technical Specifications referenced in procedures were often incomplete and sometimes incorrect.
Procedures OST 1.13.10, MSP 33.04, and MSP 33.03, specifically mentioned in the above item, have been revised so that the titles of these procedures more accurately reflect procedure contents.
For other procedures reviewed during this inspection, the procedure titles reflected procedure content.
Except as noted in Paragraph 4.d, procedures reviewed during this inspec-tion accurately referenced Technical Specifications.
Additionally, letter BVPS: JAW:596, " Consistent Document Terminology," October 11, 1978, was issued to instruct BVPS personnel preparing procedures or procedure revisions to use proper terminology.
(0 pen) Unresolved Item (78-21-01):
Procedure revisions are required to ensure periodic level checks of the spent fuel pool during refueling operations to meet Technical Specification requirements.
Licensee stated that procedure revisions would be issued following completion of modifi-cations to the spent fuel pool, currently in progress, and before next refueling, which has been delayed until September-October 1979.
(Closed) Unresolved Item (78-21-02):
Licensee needs to ensure a supply of emergency water is available to the spent fuel pool and that there is an emergency procedure for adding water to the spent fuel pool if there is a loss of spent fuel pool water.
The inspector verified that a procedure, BVPS-0M 1.33.4T, " Supplying River Water to Spent Fuel Pool Using Diese!
Water Fire Pump," Revision 6, April 4, 1979, has been issued, which will ensure a supply of emergency water to the spent fuel pool.
(0 pen)
Inspector Follow Item (78-20-06):
Date of calibration of test instrument Eb M ine MS-3 was not recorded in MSP 43.0781 and MSP 43.0782 and other procedures as required by those procedures and that the Eberline MS-3 receives an operability check rather than a calibration.
The licensee has determined that only an operability check can be done with the MS-3.
Additionally, the inspector verified that BVPS Conduct of Maintenance, Chapter 1, Section F, Revision 7, which is awaiting final approval, will require a sticker to be placed on the MS-3 showing the date of the most recent operability check.
Procedures MSP 43.08R to 43.41R, " Radiation Log Meter Area (or Process) Monitor Radiological Calibrations" (to be issued), which, in part, will replace MSP's 43.0781 and 43.07B2, will specify that the date of calibration or operability check of measurement instruments used shall be documented on the data sheets of the instrument being calibrated.
This item remains open pending final issue of procedures noted above and inspector review of these procedures.
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(Closed)
Inspector Follow Item (78-20-05):
Data for HSP 9.05, " Containment Sump Flow Measuring System Calibration" was noted as missing from the files.
The inspector determined that the data has still not been located, however, data for MSP 9.05, subsequently performed on September 8, 1978, was on file and the data was reviewed by the inspector.
Data missing from plant record files is apparently a generic problem and has been identified as an item of noncompliance in Inspection Report No. 50-334/79-04 (334/79-04-01).
This item is closed as licensee corrective action will b. provided in resolution to the item of noncompliance noted above.
(Closed)
Infraction (78-20-01):
Fire protection instrumentation surveil-lance perfomed by an outside contractor without a licensee-approved procedure.
The inspector verified that Station Administrative Directive (SAD)-2 has been revised to require that procedures used by vendors or contractors must also receive Onsite Review Committee (OSC) review and approval, and that the contractor which performs the fire protection instrumentation surveillance has issued a letter to the licensee which certifies that contractor personnel performing the fire protection surveil-lance were qualified to the contractor's Quality Assurance program which the contractor states meets the intent of Regulatory Guide 1.58.
In addition, the inspector reviewed a completed copy of OST 1.33.16 performed on April 18, 1979 in which no discrepancies were identified.
Based on the inspector review noted above, and a previous inspection review conducted during Inspection 50-334/78-34, this item is closed.
(Closed)
Inspector Follow Item (50-334/78-07, Paragraph 5):
Qualifications of maintenance personnel.
Instructions were issued by the Maintenance Supervisor, dated October 17, 1978, reminding all maintenance foremen of the requirement for maintenance p rsonnel certification.
(Closed) Noncompliance (334/78-07-01):
Failure to document post main-tenance calibrations.
Post maintenance test results were verified to have been documented for maintenance activities reviewed as described in Paragraph 10.
3.
Administrative Controls for Facility Procedures a.
The inspector perfor.ned an audit of the licensee's administrative
- ontrols by conducting a sampling review of below listed administrative procedures with respect to the requirements of Technical Specification, Section 6, " Administrative Controls"; ANSI N18.7, " Administrative Controls for Nuclear Power Plants"; and Regulatory Guide 1.33,
" Quality Assurance Program Requirements."
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Station Administrative Directive (SAD) No. 21, Charter of the
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Onsite Safety Committe, Revision 4, April 15,1977.
BVPS-0M 1.48.3, Operating Procedures, Revision 10, July 22,
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1977.
BVPS-0M 1.48.o, Administrative Controls, Revision 2, January 21,
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1977.
BVPS-0M 1.48.8, Records, Revision 2, January 21, 1977.
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No items of noncampliance were identified.
4.
Review of Facility Procedures a.
The inspector reviewed facility procedurr5 on a sampling basis to verify the following:
Procedures, plus any changes, were reviewed and approved in
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accordance with the requirements of the Technical Specifications and the licensee's administrative controls.
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The overall procedure format and content were in conformance
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with the requirements of the Technical Specifications and ANSI N18.7, " Administration Controls for Nuclear Power Plants."
Checklists, where applicable, were compatible with the step-dise
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instructions in the paocedures.
Appropriate Technical Specificatien limitations had been included
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in the procedures.
Temporary changes were made in conforman a wit.h Technical
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Specification requirements and the licensee's administrative controls.
Note: Temporary changes for procedures in addition to titose listed in the sample below were also reviewed.
b.
The following procedures were reviewed:
(1) System Operating Procedures BVPS-0M 1.12.2, Containment Vacuum and Leakage Monitoring
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System - Precautions, Limitations, and Setpoints, Revision 4, January 31, 1979.
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BVPS-0M 1.12.4, Containment Vacuum and Leakage Monitoring
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System - Operating Procedures, Revision 5, January 31, 1979.
BVPS-0M 1.24.2, Steam Generator Feedwater System - Pre-
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cautions Limitations and Setpoints, Revision 5, February 9, 1979.*
BVPS-0M 1.24.4, steam Generator Feedwater System - Operating
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Procedures, Revision 7, February 9, 1979.*
BVPS-0M 1.10.2, Residual Heat Removal System - Precautions,
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Limitatior.s and Setpoints, Revision 3, May 3, 1979.*
BVPS-0M 1.10.4, Residual Heat Removal - Operating Procedures,
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Revision 7, May 3, 1979.*
BVPS-0M 1.1.2, Reactor Cc,ntrol and Protection - Precautions,
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Limitations and Setpoints, Revision 2, November o, 1976.
BVPS-0M 1.1.4, Reactor Control and Protection - Operating
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Procedures, Revision 8, June 16, 1978.
BVPS-M 1.41A.2, Building Services Hot Wats Heating
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System - Precautions, Limitations and Setpoints, Revision 1, April 15, 1977.
BVPS-0M 1.41A.4, Building Services Hot Water Heating
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System - Operating Procedures, Revision 1, April 15, 1977.
BVPS-0M 1.44D.2, Area Ventilation System - Auxiliary
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Building - Precautions, Limitations and Setpoints, Revision 1, October 18, 1977.
BVPS-0M 1.44D.4, Area Ventilations System - Auxiliary
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Building - Operating Procedures, Revision 2, October 18, 1977.
(2) General Plant Operating Procedures BVPS-0M 1.52.4.F, Isolating a Reactor Coolant Loop, Revision 7,
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March 23, 1979.*
- Reviewed for technical adequacy.
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BVPS-0M 1.51.48, Station Shutdown - Plant Xenon Follow
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Operations, Revision 5, May 11, 1977.*
(3) Alarm Procedures BVPS-0M 1.12.4G (Al-35(43)), Containment Air Partial
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Pressure High-Low Ch. I (II), Revision 3, September 23, 1977.*
BVPS-0M 1.12.4G (Al-36(44)), Containment Air Partial
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Pressure High-High Ch. I (II), Revision 3, September 13, 1977.
BVPS-0M 1.24.4P (A7-6), Steam Generator Feed Pump Suction
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Pressure Low, Revision 2, December 14, 1976.*
BVPS-0M 1.24.4P (A7-29), Reactor Trip and Low Tavg or SI
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Main Feedwater Valve Closed, Revision 2, December 14, 1976.
BVPL-0M 1.10.40 (Al-126), Residual Heat Removal Heat
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Exchanger Discharge Low Flow A, Revision 2, December 22, 1975.*
BVPS-0M 1.10.4D (Al-125), Residual Heat Removal Pump
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Discharge Pressure High, Revision 2, December 22, 1975.
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BVPS-0M 1.1.4L (A4-126), Rod Bottom Drop, Revision 2, November 6, 1976.
BVPS-0M 1.1.4L (A4-124), Rod Control Bank D Low-Low,
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Revision 2, November 6, 1976.
BVPS-0M 1.41A.4E (A11-8), Hot Water Tank Level High-Low,
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Revision 1, April 15, 1977.
BVPS-0M 1.440.4D (A11-13), Auxiliary Building 18, Process
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Coo'ing System Off, Revision 2, October 18, 1977.
(4) Emergency Procedures
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BVPS-0M 1.53.4E-1, Loss of Reactor Coolant, Revision 14, June 7, 1978.*
- Reviewed for technical adequacy.
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BVPS-0M 1.53.4E-2, i.oss of Secondary Coolant, Revision 14,
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June 7, 1978.*
BVPS-0M 1.53.4E-8, Control Room Inaccessibility, Revision 14,
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June 7, 1978.
BVPS-0M 1.53.4E-5, Reactor Trip, Revision 14, June 7,
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1978.
BVPS-0M 1.53.4E-6, Turbine and Generator Trip, Revision 14,
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June 7, 1978.
(5). Maintenance Procedures 1-44VS-AC-11A-1M, Auxiliary Building Central Air Conditioning
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Unit Roll Filter Replacement, Revision 0, (not issued).
1-10RH-MOV-720A-B-1M, A or 8 Residual Heat Remov8 Safety
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Injection Return Fine M0V Bonnet Seal Weld, Revision 0 April 27, 1976.*
1-1RC-R-408K-11, Calibration of Rod Speed Power Mismatch
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Signal Conditioning Summator QM-RC408K, Revision 1, April 2, 1979.
1-24FW-T-2-1M, Auxiliary Feed Pump Turbine Drive Overhaul,
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Revision 0, June 30, 1976.*
1-13RS-P-1A-1M, 1A Inside Recirculation Spray Puep Ovechauls
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Revision 2, May 11, 1979.
1-1RCCA-Rod Control-SI, Inspection, Cleaning and $hutdown
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Adjustments of Full Length Pod Control System, Revision 0, December 19, 1975.
c.
The following items were noted in the area of Control of Operating Manual Change Notices - OMCN's (temporary changes) to facility operating procedures:
The following OMCN's were observed as still posted to operating
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procedures although the OMCN's had passed their expiration date.
In some instances, the OMCN's involved technical changes to the procedure of an apparent permanent nature; however, no revisions had been issued to replace these OMCN's:
- Reviewed for technical adequacy.
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OMCN 79-2 dated January 10, 1979, expired April 10, 1979.
OMCN 79-13 dated January 26, 1979, expired May 3, 1979.
OMCN 79-4 dated January 10, 1979, expired Anril 10, 1979.
OMCN 79-3 dated January 10, 1979, expired April 10, 1979.
OMCN 79-16 dated February 9, 1979, expired May 14, 1979.
OMCN 78-212 dated November 27, 1978, expired February 25, 1979.
OMCN 77-296 was noted as still posted to Paragraph 7.e of
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BVPS-0M 1.51.4C; however, an OMCN authorization was not present and the OMCN log indicated this change had been replaced by a later revision. A licensee representative stated that this paragraph was not included in the revision due to an oversight.
Two apparent handwritten changes were made to correct pressure
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values given in Paragraph 11 of BVBS-0M 1.51.4.c.
The changes were apparently made without obtaining an approved OMCN.
OMCN 77-315, dated September 8, 1977, was found posted to
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BVPS-0M 1.52.4F although it had expired December 15, 1977. A licensee representative stated that this OMCN had been superceded by a Temporary Operating Procedure which was still in effect, however, the change had not been removed due to an oversight.
Daily Log L4-10, which, in part, monitors main transformer
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parameters, has been changed by OMCN 78-212 to reflect new transformer parameter limits due to a temporary main transformer which is currently in use.
OMCN 78-212 was put into effect November 27, 1978.
On log sheets reviewed from January 1, 1979 to March 1, 1979, the correct change to log L4-10 was used.
However, from March 2, 1979 to May 31, 1979, a 92-day period, posted)ginal version of the log sheet (without OMCN 78-212 the ori was used on 77 different occasions although the temporary main transformer was still in use.
On 15 occasions, the Log L4-10, which had OMCN 78-212 posted, was used. This alteration of log sheets occurred 23 times within this period of time. As noted above, OMCN 78-212 had expired February 25, 1979.
The improper control of temporary changes noted above is contrary to Technical Specification 6.8.1, Appendix A to Regulatory Guide 1.33, and BVPS-0M 1.48.3.E.6 and constitutes a deficiency level item of noncompliance (334/79-14-01).
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d.
BVPS-0M 1.24.2, Section 3, specifies the action statement for Technical Specification 3.7.2.1.a.
During review of this procedure, it was noted that the "30 minute" time limitation required by the TS had been omitted from the procedure. A licensee representative stated that a procedure revision would be issued to correct this oversight.
This item will be reviewed on a future NRC:RI inspection.
5.
Technical Content of Facility Procedures The inspector conducted a review of facility procedures on a sampling basis, using FSAR System Descriptions, Piping and Instrument Diagrams and Technical Specifications, where necessary, to verify that procedures were sufficiently detailed to control the operation or evolution described within Technical Specification Requirements. The procedures reviewed with respect to this area are marked by an asterisk (*) in the previous paragraph, Paragraph 4 (Review of Facility Procedures) of this report.
No items of noncompliance were identified.
6.
Procedure Changes Resulting From License Amendments License Amendments (13 through 17), which included Technical Specification (TS) changes, were reviewed to verify that applicable procedures were revised as necessary to reflect these changes.
Except as noted below,
, applicable procedures were revised to reflect license amendments.
License Amendment No. 17, in part, deletes all reference to part
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length rods, based on the anticipated removal of part length rods during the next refueling outage.
Since part length rods are still installed, portions of License Amendment No. 17 deleting references to part length rods, have not been posted to controlled copies of Technical Specifications nor have applicable procedures been revised at this time.
This item will be reviewed during a subsequent NRC:RI inspection.
During review for incorporation into licensee procedures, the portion
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of License Amendement No. 17, which revises the Pressurizer heatup rate, it appeared that contrary to Technical Specification 4.4.9.1.a.
4.4.9.2, and 6.8.1, the Reactor Coolant System and Pressurizer heatup and coollown rates were not detcrmined to be within limits every 30 minutes as required during heatups and cooldowns of those systems.
This finaing was confirmed by interviews with reactor operators and senior operations personnel who stated that heatup and cooldown rates were not specifically checked every 30 minutes.
In addition, there were no licensee procedures specifying these surveil-lance requirements, however, operating procedures did specify the correct heatup and cooldown rates.
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During the inspection, the licensee issued Operating Manual Change Notice (Temporary Change) No. 79-58 to ensure monitoring of Pressurizer heatup rate every 30 minutes; and stated that other changes concerning monitoring of heatup and cooldown rates would be forthcomiis.
This represents an infraction level item of noncompliance with Tech..ical Specification 4.4.9.1.a. 4.4.9.2, and 6.8.1 (334/79-14-02).
7.
Changes to Procedures as Detailed in the Safety Analysis Report (Pursuant to 10 CFR 50.59 a and b
The inspector verified on a sampling basis that changes made to facility procedures during the past 12-month period were in compliance with 10 CFR 50.59(a) requirements and that records of these changes were maintained in compliance with 10 CFR 50.59(b),
For the procedures reviewed, the licensee had determined that 10 CFR 50.59 safety evaluation documentation was not required (no change in procedures as described in FSAR).
No items of noncompliance were identified.
8.
Checklists and Related Forms Operations Department Procedures, including checklists and related forms in working files, were reviewed to see that current revisions and on-the-spot changes were posted.
One item of noncompliance was identified and is detailed in Paragraph 4.c above.
9.
Procedures for Administrative Control of Safety-Related Maintenance The inspector reviewed the licensee's administrative controls for safet"-related maintenance as detailed in the following sections of the Beaver Valley Power Station Maintenance Manual, Chapter 1, Conduct of Maintenance:
Secticn A, General Rules for Implementation, Revision 9, September 6,
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1978.
Section B, Corrective Maintenance Procedures, Revision 5, February 2,
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1979.
Section E, Preventive Maintenance, Revision 4, February 2, 1979.
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Section G, Material Procurement, Revision 5, January 5, 1978.
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The review was conducted to acquaint the inspector with the licensee's procedural requirements in this area and as an audit with respect to Technical Specification, Section 6, Administrative Controls, Regulatory Guide 1.33, Quality Assurance Program Requirements, and ANSI 18.7, Admin-istrative Controls for Nuclear Power Plants.
No items of noncompliance were identified.
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10.
Review of Safety-Related Maintenance Activities a.
The inspector reviewed safety related maintenance conducted by the licensee on a sampling basis to verify the following:
Limiting conditions for operation were met while equipment was
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out of service; Required administrative approvals were obtained prior to initiating
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the work; An approved procedure was used where required;
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Provisions for fire protection, cleanliness, and housekeeping
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were included where applicable; Procedures used were adequate to satisfactorily perform the
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task; Required inspections were performed;
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Systems / components were functionally tested and/or calibrated
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prior to return to service;
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Applicable quality control records were available; The maintenance was performed by qualified maintenance personnel;
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and A reportable occurrence report, if required by Technical Speci-
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fications, was submitted based on a review of circumstances associated with the maintenance activity.
b.
The following completed Maintenanco Work Requests (MWR's) were reviewed to verify the above:
MWR 786674, Repair Power Range Drawer, April 29, 1978;
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MWR 781400, Calibrate Individual Rod Indicators, July 13, 1978;
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MWR 780896, Loop B Delta T, April 24, 1978;
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MWR 788254, Liquid Rad Waste Monitor, December 15, 1978;
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MWR 787976, Ventilation Duct Particulate Monitor, November 22,
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1978; MWR 781176, Pressurizer Level Control Loop, June 8, 1978;
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HWR 787644, LPSI Hot Leg Injection Check Valve, October 20,
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1978; MWR 787248, Replace RCS-Flow Transmitter By-Pass Valve, August 18,
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1978:
M'./R 780982, Loop 1 By-Pass Valve, May 5,1978;
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MWR 786583, 1A Low Head Safety Injection Pump, April 18, 1978;
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MWR 788059, Reactor Coolant Pump, December 6, 1978;
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MWR 786560, 80 rom Injection Inlet Isolation, April 10, 1978;
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MWR 786910,1B Low Head Safety Injection Pump Motor, June 12,
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197C; MWR 781645 and 781654, Containment Air Monitor Isolation Valves,
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August 17, 1978; MWR 781656, Containment Valve HCV-CV-151, August 19, 1978;
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MWR 782127, Inside Containment Air Ejector Isolation Valve,
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November 15, 1976; MWR 781595, Containment Air Ejector Suction Check, August 9,
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1978; MWR 781946, Containment Moisture Transmitter, October 9, 1978;
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MWR 781571, Battery Charger, No. 4, August 4, 1978.
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MWR 781166, No. 2 Diesel Generator, June 7, 1978; and
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MWR 788151, No. 1 Emergency Diesel Generator, December 6, 1978.
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c.
Curing the review of MWR 780896, the inspector noted that the failure of one Overtemperature Delta-T, Reactor Trip System instrument channel, which occurred on April 24, 1978, was not reported as required by Technical Specification 6.9.1.9.b.
This is considered to be an item of noncompliance at the deficiency level (334/79-14-03).
The Station Log showed that the inoperable channel was immediately placed in the tripped condition and the quadrant power tilt ratio was monitored in excess of once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as required by Technical Specification 3.3.1.1 during the period the channel was out of service.
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11.
Facility Tour On several occasions during the inspection, tours of the facility were conducted of the Turbine and Auxiliary Buildings and the Security Fence.
During the tours, the inspectors observed radiation control measures, monitoring instrumentation, housekeeping, and controls for Technical Specification compliance.
In addition, the inspectors observed Control Room operations on both day and evening shifts for Control Room manning, shift turnovers, and facility operation in accordance with Administrative and Technical Specification requirements.
No items of noncompliance were identified.
12.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncom-pliance, or deviations.
No unresolved items were identified during this inspection.
13.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on June 8, 1979 and summarized the purpose, scope, and findings of the inspection.
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