IR 05000213/1989010

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Safety Insp Rept 50-213/89-10 on 890614-0725.No Violations & No New Unresolved Items Noted.Major Areas Inspected:Plant Operations,Radiation Protection,Fire Protection,Security, Maint,Surveillance Testing,Open Items & Safety Sys Lineups
ML20246F403
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 08/18/1989
From: Haverkamp D
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20246F394 List:
References
50-213-89-10, IEB-79-18, NUDOCS 8908300315
Download: ML20246F403 (150)


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Report No.

50-213/89'-10 Docket No.

50'-213 License No.

DPR-61 Licensee:

. Connecticut Yankee Atomic Power Company Har fo 06101

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Facility:

.Haddam' Neck Plant, Haddam Neck, Connecticut-Inspection at:

Haddam Neck Plant Inspection dates:

June 14, 1989 through July 25, 1989 Inspectors:

Andra'A. Asars, Resident Inspector o.

John T. Shediosky, Senior Resident Inspector Approved by:

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(f. ft. Haverkamp, Chief /

"Dat'e Jdctor Projects Section 4A R

Summary:

Inspection 50-213/89-10 (6/14/89 - 7/25/89)

Areas Inspected: This was a routine safety inspection by the resident inspec-tors. Areas reviewed included plant operations, radiation protection, fire protection, security, maintenance, surveillance testing, open items, safety I

system lineups, cable vault ground water in leakage, and licensee response to an. inoperable charging system valve.

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'Results:.No violations were identified and no new unresolved items were opened. Two open items regarding an inadequately controlled containment l'

' penetration boundary valve and evaluation of the equipment qualification of four. motor-operated valves were closed.

Two open items concerning the audibil-ity of the plant paging system and implementation of the Augmented Inservice Inspection Program were updated. No unacceptable conditions were identified.

8908300315 890819 PDR ADOCK 0"400213

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TABLE'0F CONTENTS N

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'1.

S umma ry of Fa c i l i ty Acti v i ti e s.......,............... I

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. Plant Operations........................,..

'2.1 Sa fe'ty System ' Wal kdown.........................

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F 2.2; Ground Water Leakage into the Cable Vault.,........

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Plant Operations Review Committee

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~4. - ' Maintenance and Surveillance Testing................

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' 4.1-l Inoperable Emergency Diesel Generator 2A

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4.2 Simulator Verification of Integrated Electrical Tests......

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Fol l owu p o f Open I tems....................... - 5

' 5.1 Bulletin 79-18,' Audibility of Evacuation Alarm.in High Noise Areas............................ 5 5.2 - Uncontrolled Containment Penetration Boundary Valve...... 6 5.3 Evaluation and Qualification of New Motor Operated Valves...

5.4-Inadequacies -in Auxiliary Feedwater Inservice Inspection Program..

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Events Occurring During the Inspection............... 7 6.1 Licensee Event Reports and Safeguards Event Reports...... 7 6.2 Inoperable Charging System Motor Operated Valve........ 7 7.

Review'of Periodic and Special Reports............... 9 8.

Allegation RI-89-A-0065, on Fitness for Employment.

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9.

Management Meetings...................

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DETAILS

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Summary of Facility Activities (71707)

At the beginning of the' inspection period, the plant was operating at

.approximately 65% power and increasing power at 5% per day for fuel management considerations.

Full power operation was attained on June 20 and continued through the.end of the inspection period.

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2.

. Plant Operations (71707, 71710)

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The inspectors observed plant operation, radiological contro1~, physical, security and test procedure verification activities during regular tours of the following plant areas:

Control: Room-Primary Access Point

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Primary Auxiliary Building Fence Line (Protected Area)

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Vital Switchgear Room Yard Areas

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Diesel Generator Rooms

. Turbine Building

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' Radiological Control Point Intake Structure

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Appendix R Switchgear Building Auxiliary Feedwater Pump Room

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Plant Simulator Technical Training Facility

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L Control room instruments were observed for correlation between channels and for conformance with Technical Specification requirements. The inspectors observed various alarm conditions which had been received and acknowledr.ed; operator awareness and response to these conditions were reviewed. Control room and shift manning were compared to regulatory requirements.

Posting and control of radiation and high radiation areas t

was inspected.

Compliance with radiation work permits and use of appro-priate personnel monitoring devices were checked. Plant housekeeping controls were observed, including control and storage of flammable materi-al and other potential safety hazards. The inspectors also examined the condition of various fire protection systems.

During plant tours, logs and records were reviewed to determine if entries were properly made and communicated equipment status / deficiencies.

These records included operating logs, turnover sheets, tag out.and jumper logs, process computer printouts, and plant information reports. The inspectors observed select-ed aspects of plant security including access control, physical barriers, and personnel monitoring.

In addition to normal utility working hours (7:00 a.m. to 3:30 p.m.) on week days, the review of plant operations was routinely conducted during portions of the weekend and during backshift (midnight or evening) working hour. Weekend and backshift inspection was provided on the following days:

June 18, 1989 11:00 a.m. through 6:00 p.m.

July 13,1989 until 8:00 p.m.

July 15, 1989 10:30 a.m. through 4:00 p.m.

No unacceptable conditions were identified. Operators were alert and displayed no signs of inattention to duty or fatigue.

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2.1 ' Safety System Walkdown In addition to routine observations made during regular plant tours,.

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the inspectors conducted walkdowns. of the accessible portions of the safety-related systems listed below.

Emergency Diesel Generators

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Steam' Generator Auxiliary Feedwater -

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The inspectors' verified system operability based upon reviews of'

valve lineups,. control-room system' prints, equipment conditions, instrument calibrations, surveillance test frequencies and results, and control. room indications.

2.2 Ground Water leakage into the Cable Vault Du' ring the. spring months when the area water table.is abnormally high, the plant-experiences water leakage into the cable vault. The leakage is primarily through the floor and selected conduit bank openings. This issue was previously addressed in NRC Inspection Report 50-213/87-18, Detail 6.1 and reported in LERs (Licensee Event Reports) 50-213/87-07.and 87-07-01.

The cable vault is a single, underground room which houses all of the safety related electrical penetrations to the containment. There are two sumps but no permanently installed sump pumps. Also, the floor is not graded to permit natural water flow to the sumps. The poten-tial exists; for submerging.five safety related electrical penetra-tions. Two flood alarms were installed in 1987 to alert operators to high water levels on the cable vault floor. Additional sealing material has also been applied to the floor and walls.

During this inspection period, the floor and conduit banks in the cable vault have leaked again, resulting in the accumulation of water in floor low spots.

The licensee's temporary solution to this problem has been to manually squeegee the standing water to the sumps and use portable sump pumps.

The inspectors readdressed the concern of the collection of water in the cable vault with engineering and station management. The inspec-tors were informed that a water study of the area has been completed which identified a natural water flow path under the cable vault.

Several recommendations were made for arresting the problem. The licensee is currently evaluating these options for implementation.

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Until a permanent solution is reached, the licensee will continue to mop and pump the water that collects on the cable vault floor.

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inspectors will continue to monitor dewatering activities and progress towards development of a permanent solution.

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3.

Plant Operations Review Committee (40500)

The inspectors attended several Plant Operations Review Committee meetings.

Technical-specification 6.5 requirements for required member attendance.

were' verified.* The meeting agendas included procedural changes, proposed changes to the Technical Specifications.and Plant Design Change Records.

The meetings were characterized by frank discussions and questioning of the proposed changes.

In particular, consideration was given to assure clarity and consistency among procedures.

Items for which adequate review time was not available were postponed to allow committee members time to review and comment. Dissenting opinions were encouraged and resolved to the satisfaction of the committee. The inspectors had no.further comments.

4.

Maintenance and Surveillance Testing (61726, 62703)

The inspectors observed various maintenance and problem investigation activities for compliance with requirements and applicable codes and standards, Quality Services Department involvement, safety tags, equipment alignment and use of jumpers, personnel qualifications, radiological con-trols, fire protection, retestvragd deportability. Also, the inspector witnessed selected surveillance tests to determine whether properly approved procedures were in use, test instrumentation was properly cali-brated and used, technical specifications were satisfied, testing was performed by qualified personnel, procedure details were adequate, and test results satisfied acceptance criteria or were properly dispositiened.

Portions of the following activities were reviewed.

PMP 9.1-8, Low Pressure Steam Dump System Test.

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ST 11.7-1, Audibility Verification of Plant Paging System Outside

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Containment.

SUR 5.1-4, Core Cooling Systems Hot Operational Test.

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SUR 5.1-17A, Emergency Diesel Generator 2A Manual Starting and Loading

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Test.

SUR 5.1-178, Emergency Diesel Generator 2B Manual Starting and Loading

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Test.

Emergency diesel generator 2A tachometer troubleshooting.

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Spent fuel storage cooling heat exchanger maintenance.

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The inspector also observed special test procedure verification through the use of the plant simulator of:

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.ST 11.7-12, 1989 Refueling Outage' Plant (Emergency Safeguards Sys-

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.U tems) Integrated Test.

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ST 11.7-13, "B" Switchgear (Appendix R Remote Shutdown) Compliance

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ST 11.7-14, Appendix "R"-Service Water Performance Test.

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4.1 : Inoperable Emergency Diesel Generator 2A

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On July 11 at' 11:25 a.m., emergency diesel generator (EDG) 2A was declared inoperable due to failure to meet the acceptance criteria of SUR 5.1-17A. When the EDG was initially started and operated at idle speed (450 rpm), the engine tachometer indicated a speed of approxi-mately 300 rpm. 'After a short period, the tachometer indication jumped to 450 rpm. The engine was brought to full speed (900 rpm)

and the tachometer responded as expected. However, SUR 5.1-17A requires an engine start time of eight seconds measured between starting and reaching an idle speed of 450 rpm..This criteria was not met due to the apparent sticking of the tachometer.

EDG 2A was declared inoperable and the operability of EDG 28 was verified as required by Technical Specification 3.12 at 12:18 p.m.

Vendor technical manuals indicated that this type of erratic tachome-ter operation could be caused by dirty brushes in the instrument generator. A second tachometer which is used for engine overspeed testing was installed and EDG 2A was restarted. Both tachometers responded as expected.

EDG 2A was declared operable and returned to standby at 6:18 p.m.

Surveillance testing and electrical maintenance troubleshooting activities were observed. The inspector also verified that the requirements of the Technical Specifications were met.

No deficiencies were identified.

4.2 Simulator Verification of Integrated Electrical Tests The inspector observed portior.s of a procedure verification for integrated emergency safeguards system electrical tests. The plant simulator was used to aid this process on July 6, 7, 20, and 21.

These tests are intended to demonstrate the correct integrated response of all modifications involving the reactor protection, emergency core cooling and containment isolation systems at the completion of the 1989 refueling outage. All tests are to done with the reactor in cold shutdown. The following summarizes the strategy taken in these tests:

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Containment isolation and safety injection tests are. intended to.

demonstrate system operability for each of the two safety divisions

.with the redundant division emergency electrical buses deenergized.

These: tests will be initiated through containment pressure-instruments.

Containment. isolation and safety injection system tests will be repeated for each division with a partial loss of AC emergency-electrical power.

Prcper starting and loading of the emergency diesel generators is included.

A loss of offsite electrical power test is intended to demon-strate the operability of the emergency diesel generators, the associated electrical-bus control systems, and the service water -

system.

Finally, containment isolation and safety injection systems testing accompanied by a loss of offsite electrical power conclude Special Test ST 11.7-12, 1989 Refueling Outage Plant Integrated. Test.

The ST 11.7-13, "B" Switchgear Compliance Test, is to demonstrate the operability of plant equipment needed to comply with 10 CFR 50, Appendix R.

The test simulates a fire in various plant locations, directs electrically deenergizing equipment in that location and verifies that alternate. equipment and instrumentation is operable from remote locations.

Fires are assumed sequentially in each of the following locations: the Control Room, the "A" (old) Switchgear Room, and the "B" (new) Switchgear Room.

The ST 11.7-14, Appendix "R" Service Water Performance Test, is to demonstrate the capability to align the service water system to support emergency safeguards systems components during the most

. restrictive configuration determined during the 10 CFR 50, Appendix R

. analysis.

The inspector observed that the plant simulator proved to be a valuable tool during the procedure validation process of these complex evolutions.

There were no unacceptable conditions identified.

5.

Followup of Open Items (61726, 62703, 71707)

5.1 Bulletin 79-18, Audioility of Evacuation Alarm in High Noise Areas l

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(0 pen) Bulletin (79-18) This bulletin concerns potential inaudibili-

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ty of the station evacuation alarm in high noise areas.

Licensees were requested to evaluate the acceptability of installed public address systems.

This issue was previously discussed in NRC Inspec-tion Report 50-213/86-27. During this inspection period, the inspec-tors observed licensee performance of ST 11.7-1, Audibility Verifica-tion of Plant Paging System Outside Containment.

Plant page an-nouncements were monitored at chosen locations outside of containment

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i tol determine adequacy. This item will. remain open pending audibility testing of the page system inside of containment.

'5'.2 ! Uncontrolled Containment Penetration Goundary Valve (Closed) Violation (89-05-01) The licensee identified, during a

.walkdown inspection in support-of' local leak-rate surveillance procedure validation, that' PW-V-600 was mislabeled and not locked

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' closed 'as required by SUR 5.1-126, Locked Valve Checklist. Correc-

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tive actions for this violation were taken immediately and are discussed in NRC Inspection Report 50-213/89-05. The licensee responded to this violation by. letter dated June 12, 1989. The root cause of the inadequate. control of the containment penetration boundary valve was determined to be human error. The inspectors reviewed the'. licensee's response and corrective actions; these were

' determined to.be adequate.

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5.3: ' Evaluation and Qualification of New Motor Operated Valves (Closed) Unresolved Item (87-28-07) This item involved the qualifi-cation of four pressurizer relief isolation valves wtich were omitted from the MEPL (Master Equipment and Parts List).

Valves PR-MOV-596,

-597, -598, and -599 were being installed durit g the 1987 Refueling Outage when.this was identified.

Prior to completion of installa-tion, the valves were evaluated and included in the MEPL. The inspector reviewed the evaluation and verified that these valves appear in the MEPL.

5.4 Inacequate Implementation of Augmented Inservice Inspection of Auxiliary Feedwater (0 pen) Unresolved Item (87-28-01) Inadequacies were_ identified in the implementatini of the Augmented AFW ( Auxiliary Feedwater) System ISI (Inservice Inspection) Program.

The licensee had submitted a TS (Technical Specification) Change Request which incorporated the proposed AFW ISI Program as a formal surveillance requirement. An audit of the program implementation. identified the following four discrepancies. The inspector reviewed the corrective actions for each of these items.

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Actual number of AFW welds differs from TS number. This dis-crepancy was corrected by TS Amendment No. 106, dated October 3, 1988, 2.

The computerized ISI Work Plan did not provide for the correct intervals for nondestructive examination of AFW welds. The inspector verified that the current work plan contains the correct inspection intervals.

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It was unclear whose responsibility it was for the monthly visucl inspection of the AFW welds. The licensee credits the

shift operator tours of the Terry Turbine Building to identify high energy steam or large amounts of condensation from a weld leak. Additionally, SUR 5.1-24, Inspection of Main Steam Header, Main Steam Lines and Main Feed Lines, is conducted monthly to inspect for visible signs of leakage from the steam

lines including those to the AFW pump turbines.

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One hundred percent weld inspection was proposed, 50% inspection was documented. This part of the open item will remain open pending further NRC review of the inspections performed.

6.

Events Occurring During the Inspection (71707, 92700, 93702)

6.1 Licensee Event Reports and Safeguards Event Reports The following licensee event reports (LERs) and safeguards event reports (SERs) were reviewed for clarity, accuracy of the description of cause, and adequacy of corrective action. The inspector:, deter-mined whether further information was required and whether there were generic implications. The inspectors also verified that the reporting requirements of 10 CFR 50.73, 10 CFR 73.71, and station administrative, operating, and security procedures had been mat, that appropriate corrective action had been taken, and that the continued operation of the facility was conducted within Technical Specifica-tion Limits.

89-S03 Safeguards Event Report 89-504 Safeguards Event Report 89-09 Momentary Loss of Emergency Bus Due to Operator Error (NRC Inspection Report 50-213/89-07)

89-10 Surveillance Procedure Determined Inadequate (NRC Inspection Report 50-213/89-07)

No unacceptable conditions were identified.

6.2 Inoperable Charging System Motor-Operated Valve On July 14, while restoring the normal charging system alignment, a motor-operated valve in the flow path failed to open.

The alternate letdown path had been in service earlier that day for flushing of an ion exchanger. When operators were restoring the normal system alignment, valve CH-MOV-292B failed to fully open.

The valve was declared inoperable; maintenance personnel were notified; and a plant information report was initiated.

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Valve CH-MOV-292B is one of two parallel, full flow, motor-operated gate valves i_n the charging flow path between the regenerative heat exchangers and the discharge to the reactor coolant system.

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valves are located in the outer annules of the Containment lower level. During-normal operation, they are maintained in the open position. They also are required to open on a safety injection signal. As a compensatory measure, the parallel valve CH-MOV-292C was opened, power removed, and red tags placed on the control room hand switch, the breaker, and the operator hand wheel in containment to ensure that the charging flow path is available.

Initially, the motor-operator appeared to have tripped on thermal overload. The thermal overload relay was replaced, however the valve still failed to open. A containment entry was made for further investigation. The valve could not be operated locally with the hand wheel and appeared to be mechanically stuck.

Haddam Neck Plant TS (Technical Specifications) 3.6 (A)(3) requires that the reactor not be critical unless the system valves and inter-locks required for proper operation of core cooling systems are operable. A Plant Operations Review Committee (PORC) meeting was held in the control room on July 15 to discuss the consequences of this valve failure, necessary procedure changes, and any additional compensatory measures. The PORC determined that the measures taken to ensure that CH-MOV-292C remains open were sufficient to meet the intent of TS 3.6 (A)(3).

The charging system is the injection path for a small break LOCA and is also taken credit for in the recirculation phase of a safety injection for " feed and bleed" of the Reactor Coolant System.

Failure of one of these parallel valves to open is assumed in the safety analysis.

The inspector reviewed the surveillance tests and performance histo-ries for CH-MOV-292B and -292C. The acceptance criteria for SUR 5.7-20, Inservice Testing of Charging Line Stop Valves, included valve closing time requirements as part of the operability determina-tion.

The inspector questioned why the closing and not the opening time determined operability since the safety function of the valve is to open.

Engineering personnel reviewed the safety analysis assump-tions for these valves and determined that no opening or closing times were assumed since the valves are normally open. The licensee is incorporating the necessary procedure changes to make the accep-tance criteria more appropriate.

The inspector attended the PORC meetings, reviewed licensee actions in response to this valve failure, and reviewed the valve performance history and surveillance tests.

The compensatory measures were determined to be adequate; no deficiencies were identified.

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Review of Periodic and Special Reports'(90712)

Upon receipt, periodic and special reports submitted pursuant to Technical Specification 6.9 were reviewed. This. review verified that the reported i

information was valid'and included the NRC required data; that test results and Lsupporting information were consistent with design. predictions and performance specifications; and that planned corrective actions.were adequate.'for resolution of the. problem. The inspectors also ascertained

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whether any reported information sh' uld be classified as an abnormal o

occurrence. The following reports were reviewed:

Haddam Neck Monthly Operating Report 89-05, for the period May 1,1989 through May 31, 1989

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Haddam Neck Monthly Operating Report 89-06, for the period June 1,- 1989 through June 30, 1989 No unacceptable conditions were identified.

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Allegation RI-89-A-0065, on Fitness for Employment The inspector received an anonymous allegation by telephone on May 2, 1989 which questioned an individual's fitness for employment.

Similar informa-tion was contained in an anonymous letter dated May 17, 1989. Based on this document, which was received on May 23, the Region I Allegation Board directed the Haddam Neck Plant NRC Senior Resident Inspector (SRI) to discuss the content of the allegation with the licensee. On May 23 the SRI. met with the Station Superintendent, who agreed to investigate the allegation through an internal audit of the process for security access to station protected and vital areas.

These audits began on May 24 and included people from several organiza-tions to broaden the scope of the audit and to improve its effectiveness.

The audit included a review of the security access programs and process l

for several organizations. The licensee verified the findings of pre-employment personal background inve9 igations and the results of personality profile tests for several persons employed by those organiza-l tions. The pre-empicyment statements were reviewed to verify that the information provided was correct.

The audit was complete and the results presented to the SRI on June 28.

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The licensee concluded that those organizations who maintain programs to support personal access to the Haddam Neck Plant security areas were functioning within the requirements of the Station Security Plan.

Specif-ically concerning this allegation, there was no reason found to disqualify the named person's security access authorization.

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c-Additionally, the person named within the al',cgation contacted.the SRI and e

. licensee security. personnel and offered to cooperate in this investigation l

. following a newspaper story. The' author had apparently sent copies ~of the allegation to two Connecticut papers; the Hartford Courant chose to make

coverage in its May 24. edition.

The' licensee's investigation was discussed in detail with the NRC inspec-

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tor during its progress,' there were no unacceptable conditions 11dentified.

This allegation is closed.

9.

Management Meetings-(30703, 35502)

On July 21, the inspector attended the Mid'-SALP Management Meeting between Northeast Utilities and.NRC Region I management. The meeting agenda included discussions of plant operations during this SALP period, licensee initiatives, self-assessment programs, and refueling outage scope.

Attachments 1, 2 arid 3 to this report were presented by the licensee during;the meeting.

Meetings were also held with station management as needed tc discuss inspection findings. A summary of the findings was discussed at the exit meeting. No proprietary information related to this inspection was identified and no written material was given to'the licensee.

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