IR 05000397/1986006

Insp Rept 50-397/86-06 on 860203-0314.Violation Noted: Pressure Gas Bottle Improperly Stored in Reactor Bldg

ML17278A713
Person / Time
Site:	Columbia
Issue date:	04/04/1986
From:	Rebecca Barr, Dodds R, Johnson P, Toth A, Willett D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML17278A711	List: IR 05000397/1986006 ML17278A710 ML17278A712
References
50-397-86-06, 50-397-86-6, IEIN-85-042, IEIN-85-049, IEIN-85-42, IEIN-85-49, NUDOCS 8604220327
Download: ML17278A713 (20)

Text

U.S.

NUCLEAR REGULATORY COMMISSION REGION V Report No:

50-397/86-06 Docket No:

50-397 Iicensee:

Washington Public Power Supply System P.

O. Box 968 Richland, Wa.

99352 Facility Name: Washington Nuclear Project No.

(WNP-2)

Inspection at:

WNP-2 Site near Richland, Washington Inspection Conducted:

February

- March 14, 1986 Inspectors:

A. D. Toth, Senior Resident Inspector February 12-14, 1986 0-6-A Date Signed Summary:

R. T. Dodds, Chief Reactor Projects Section

February 17-21, 1986 P~~W ~

R.

C. Barr, Resident Inspector PPQ ~

P.

H. Johnson, Chief Reactor Projects Section

February 26-28, 1986 PQ L+

D. J. Willett, Reactor Inspector WIZt wz P.

H. Johnson, Chief Reactor Projects Section

te ig ed Date Signed Date Signed Date igned Date Signed Ins ection on Februa 3-March 14 1986 (50-397/86-06)

Areas Ins ected:

Routine inspection by the resident inspector and region based inspectors of control room operations, engineered safety feature (ESF)

status, surveillance program, maintenance program, licensee event reports, special inspection topics, and 'licensee action on previous inspection findings.

During this inspection, Inspection Procedures 30703, 39701, 40700, 40704, 42700, 62703, 61726, 71707, 71710, 90712, 92700, 92701 and 93702 were covered.

Results:

One violation was identified (gee paragraph 4.a).

8b04220327 8b0407 PDR ADOCH, 05000397

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DETAILS 1.

Persons, Contacted J.

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Martin, Assistant Managing Director for Operations Powers, Plant Manager Baker, Assistant Plant Manager Hosier, Nuclear Safety Assurance Group (NSAG) Manager Godfrey, Performance Evaluation Manager McGilton, Operational Assurance Program DaValle, Principal Engineer (NSAG)

Dennison, Principal Engineer (NSAG)

Morrison, Chemistry Engineer Worthen, Operations Engineer

,Beardsley, Assistant Operations Manager Harmon, Maintenance Manager Little, Planning/Scheduling Supervisor Cowan, Plant Technical'anager Davison, Compliance Engineer Mertens, QA/QC Compliance Engineer Feldman, Plant Quality Assurance Manager Peters, Administrative Manager Powell, Licensing Manager Graybeal, Plant Chemistry Manager Corcoran, Plant Operations Manager

• Personnel in attendance at exit meeting The inspectors also interviewed various control room operators; shift supervisors; shift managers; and engineering, quality assurance, and management personnel relative to activities in progress and records.

2.

General The Resident Inspector was on site February 3-7,10-14, 18-21, 24-28 and March 3-6, 1986.

Backshift inspections were conducted February 4, 5,

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18 21 E

24E

E 27 E and March 3 6 1986

, Other NRC personnel visited the site this month for routine activities as follows:

Senior Resident Inspector (A. Toth) was on site February 12-14, 1986.

Region V Project Inspector (P. Quails)

and Reactor Inspector (K.

Ivey) were on site February 3-7, 1986.

Region V Reactor Projects Section 1 Chief (R. Dodds)

was on site February 18-21, 1986.

Region V Reactor Projects Section 3 Chief (P. Johnson)

was on site February 26-28, 198 C ~

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t Region V Reactor Safety Branch Chief (R. Pate)

was on site February 3-7, 1986 to administer licensing examinations.

Region V Project Inspector (P. Quails)

and Reactor Inspector (P.

Phelan)

accompained by consultants (R. Hodor and J. Higgins) from BNL were on site March 3-7, 1986.

Region V Reactor Inspector (D. Willett) was on site March 12-14, 1986.

Nuclear Reactor Regulation Iicensing Project Manager (J. Bradfute)

was on site March 6 and 7, 1986.

3.

Plant Status During the month of February the plant, limited by an out-of-service recirculation pump, operated at about 72% power except for approximately 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of 50/ power operation on February 21 for the examination of a circulating water pump and 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on February 28 for dispatch.

Through March 14 the plant continued single loop operation at 50-72/ power as required 'by load demand.

4.

0 erations Verifications The resident inspector reviewed the control room operator and shift manager log books on a daily basis for this report period.

Reviews were also, conducted to verify that there were no conflicts with Technical Specifications.

Selected events involving unusual conditions of equipment were discussed with the control room personnel available at the time of the review and evaluated for potential safety significance.

The licensee's adherence to Limiting Conditions for Operation (LCO's),

particularly those dealing with ESF and ESF electrical alignment, were observed.

The inspectors routinely took note of activated annunciators on the control panels and ascertained that. the control zoom licensed personnel on duty at the time were familiar with the reason for each annunciator and its significance.

The inspectors observed access control, control room manning, operability of nuclear instruments, and availability of onsite and offsite electrical power.

The inspectors also made regular tours of accessible areas of the facility to assess equipment conditions, radiological controls, security, safety a'nd adherence to regulatory requirements.

a.

During this period the inspectors p'erfozmed a follow-up review of housekeeping in low traffic areas of the plant.

The inspectors observed a nitrogen gas cylinder in the RHR 'A'ump room, attached to the RHR 'A'ump seal discharge line by light gauge wire.

This constituted a potential hazard to a safety related system, since the mass of the nitrogen cylinder was not considered in the seismic analysis of the system.

The NRC has identified, in NUREG/CR-3551, The Safety Implications Associated With In Plant Gas Storage and Distribution Systems In Nuclear Power Plants, that a significant, safety hazard exists if the bottle gets damaged.

A potential hazard to the RHR A/LPCI pump also existed here.

If the wire fastener, to the RHR piping 'was stzong enough to cause damage to the seal water

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line and if the bottle were to be inadvertantly knocked over, then the pump could concievably have been rendered inoperable.

The issue involving improper high pressure gas bottle storage has been identified to the licensee in previous inspection reports 85-05 and 85-22 and is not consistent with his fire protection program implementation (license condition 2.c.l4).

This is a violation of license condition 2.c(14) (86-06-01).

The above obsi rvations indicated a need for additional management attention to housekeeping in low traffic areas.

(86-04-01, Open)

b.

The Equipment Clearance and Tagging procedure (PPM 1.3.8)

was evaluated and its implementation assessed.

The procedure was thorough and clear; however, implementation of the procedure was noted to 'require improvement.

Examples included required redundant verification of tag removal not performed, a clearance released but not authorized, and tags added but not authorized.

These items were brought to management,'s attention and identified as inadequate thoroughness in implementation of an administrative control., Future inspections will focus on improved implementation of the clearance order procedure.

(86-06-02)

5.

Surveillance Pro ram Im lementation The inspectors ascertained that surveillance of safety-related systems or

'omponents was being conducted in accordance with license requirements.

Xn addition to witnessing and verifying daily control panel instrument checks, the inspectors observed portions of several surveillance tests by operators and instrument and control technicians.

Surveillance tests observed were:

PPM 7.4.3.6.1.1 Control Rod Block Monitor PPM 7.4.3.6.3.2 Control Rod Block, APRM B-Channel Functional Test PPM 7.4.3.6.3.3 Control Rod Block, APRM C-Channel Functional Test PPM 7.4.3.2.1.72 Reactor Core Isolation Cooling Pipe Routing Area Temperature High No violations or deviations were identified.

6.

Monthl Maintenance Observation Portions of selected safety-related system maintenance activities were observed.

By direct observation and review of records the inspector determined that these activities were consistent with ICOs, the proper administrative controls and tag-out procedures were followed, and equipment was properly tested before being returned to service.

The inspector also reviewed the outstanding job orders to determine if the licensee was giving priority to safety related maintenance and to verify that backlo'gs which might affect system performance were not developin ~ ~

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1'o violations or, deviations were identified.

7.

En ineered'afet Feature Verification The inspector verified the operability of the High Pressure Core Spray System, the Low Pressure Coze Spray System and the Reactor Core Isolation Cooling System, by performing a-walkdown of the accessible portions of each system.

The inspector confirmed that the licensee's system lineup procedures matched plant drawings and the as-built configuration, and verified that valves were in the proper position, had power available, and w'ere locked as appropriate.

The licensee's procedures were verified to be in accordance with the Technical Specifications and the FSAR.

Maintenance performed on February 5, 1986 on the "A" Main Feed system was observed.

No violations or deviations were identified.

8.

Licensee Event Re orts The resident inspector reviewed the reports and their supporting information to verify that licensee management had reviewed the event, corrective action had been taken, no unresolved safety questions existed, and violations of regulations or Technical Specification conditions, if any, had been identified.

The followup actions committed to were in the process of being verified.

LER-83-01 (open)

Rod Block Interlock on Fuel Handling System LER-84;,08 (open) Failure of Suppression Pool Level Indicator No violations were identified.

9.

Followu on IE Information Notice's IN-85-42, Loose phosphor in 'Panasonic 800 seried TLD:

Records were reviewed verifying the Supply System does not utilize the cited model.

In addition, actions had been taken to preclude procuring the cited model.

IN-85-49, Regarding relay calibration problem:

Records were reviewed verifying the Supply System does not calibrate or utilize the 'relay in the horizontal position.

10.

Licensee Actions On Previous NRC Ins ection Findin s The inspectors reviewed records, interviewed personnel, and inspected plant conditions relative to licensee actions on previously identified inspection findings:

a

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(Closed) Followup Item (84-15-01) - Seven specific weaknesses were identified during an NRC team inspection of operating crew

performance.

The licensee responded to the inspection findings via an August 23, 1984 letter to NRC.

An amended reply was submitted September 20,

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1984.

The licensee's actions in the areas of question were reviewed by the resident inspectors on a routine 'basis, and some of the items were identified as resolved in prior inspection reports'.

The following review identifies those items previously closed and those, subject to continuing review.

Item a (Closed) Shift Turnover Practices

- Control Room shift turnover practices had improved, including revision of the turnover check sheet and panel walkdowns.

Efforts were made to reduce numbers of personnel in the control zoom, to reduce noise levels during the periods of shift turnover.

These included" memos to staff and signs posted to preclude personnel from control room access during shift turnover periods.

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Item b (Closed) Operator Not at the Controls - Resolution of this item was documented, in inspection reports 84-34 and 85-36.

(3)

Item q (Open)(Renumbered 86-06-03) - Awareness of Plant Status Annunciators.

The team inspection found individual operators'nowledge of annunciated plant, conditions sometimes weak.

Dur'ing subsequent routine inspections (eg., report 85-35)

NRC inspectors occassionally also found weaknesses in individual operators'amiliarity with the current condition of

'nnunciated equipment, status of corrective actions, or required actions prescribed by annunciator procedures.

This area will be subject to continuing review.

(4) 'tem d (Closed) - Independent Verification.

Since the team in'spection, surveillance procedures had been extensively revised to include independent verification provisions.

Operational system lineup procedures under revision had had independent verification steps incorporated under the procedure review guidelines issued in September 1985.

Further improvements may be warranted in the operations area, but no significant implementing errors were identified to warrant retention of this matter as an open NRC item.

(5)

Item e (Closed) - Senior Management, Visibilityin the Control Room.

Routine observations by the resident inspectors noted senior plant management routinely in the control room.

Infrequent corporate staff visits to the plant areas were also noted.

(6)

Item f (Open)(Renumbered 86-06-04) - Adequacy of Operator and Shift Manager logs. After the team inspection in June 1984, the NSAG completed a review of log data and effected a change to the applicable procedure to include INPO guidelines.

The log detail had improved to include the types of data identified by the NRC team; however, the resident inspectors identified some minor discrepencies (eg., report 85-15) which warrant continued assessment of this area during future inspections.

(7)

Item g (Closed) - Questionable Work Practices.

Special ladders were made available in the control room for access to vertical

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panels.

Special tags were issued for identification of problems with controls/annunciators.

A list of problem annunciators and corrective action status was being routinely posted in the Shift Manager's office.

Procedures call for shift manager's signature/approval of any miscellaneous information notices in control panels.

ll.

Licensee Im lementation of Commitments Described at the Zebrua 1985 Enforcement Conference Specific violations and followup items were identified in NRC inspection report 50-397/85-09.

Their acceptable resolution was described in inspection reports 85-32, 85-36 and 85-38.

The associated licensee event report (LER-85-008)

was closed in inspection report 85-08.

Inspection report 85-08 included as an attachment

%he licensee's presentation at the enforcement conference.

The attachment addressed the specific'iolations and contained statements of more general near term and long term engineering and management initiatives.

During the current report period the inspector met with plant and corporate managers to obtain their views and any supporting data that reflect on the more general commitments.

Supply System management did not develop an overall action plan for implementing, reporting and progress monitoring of the specific goals.

However, engineering items were entered into the plant tracking log, required procedure changes were included in the Plant Operations Committee action item log and LER commitments were entered into the compliance commitment tracking system.

Other more general matters were addressed by the plant manager in the routine conduct of business.

The following items of Section III of the attachment to report 85-09 were reviewed by the inspector:

a ~

Lack of Management/Supervisory Review of Decision Making Process Past inspections observed management actions directed toward developing a team spirit and efforts to orient the overall staff toward the support of operations.

This has been translated into work priorization and budgeting approval elements appearing in a variety of plant procedure and work documents.

The avoidance of punitive measures, for the sake of team building, was on occasion translated into lack of investigation and correction of matters involving personnel error (e.g.,

an occassion when an unidentified worker left a plastic chemical bag in the standby liquid control tank).

With regard to logkeeping practices, the licensee revised the applicable procedure following the June 1985 NRC team inspection to comply with the INPO good practices document; however, inspectors continue to find minor omissions in the log books. This area has been identified for future evaluation.

The general matter of management/supervisory review had shown some improvement.

b.

Reportability Aspects of the Event n

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The resolution of this matter was discussed in inspecton report 85-38.

Instructions to shift technical advisors were issued via memorandum but not included in procedure 1.3.5.5.A.5 (which more permanently documented the responsibilities of the shift technical advisor).

However, interviews with the STA's indicated awareness of their obligations to assist in determinations of reportability.

C.

Operator Knowledge of Diesel Generator Operation As documented in an August 2, 1985 simulator change request

$/l948, operator training program changes were made and simulator changes completed.

d.

Improved Design of Diesel Generator Voltage Regulation Plans were proceeding to provide slow-start and post-operation idle capability using an electronic governor for which seismically qualified equipment is not yet available.

The design change package had not yet been, issued.

A design change package and work order had been prepared for the April 1986 refueling outage for new automatic setpoint adjustment features.

It was evident the licensee was proceeding with the committed evaluations/changes.

e.

Post Trip Report and Transient Response Evaluation Improvement The NSAG and Plant Technical reviews were completed and procedures revised (June 1985) to incorporate INPO guidance.

Checklists and assessment guidance were added.

There appeared to be no formal written delegation of responsibility to technical and operations departments to improve completeness of the trip records, although procedure 1.3.5 detailed the particular information to be gathered.

Additional procedure changes were planned to incorporate independent staff members in the event assessment.

Of particular note in the existing procedure was the requirement for on-shift personnel to convene in. a meeting shortly after an event to discuss personal observations and perceptions.

Technical Specification Change Regarding Voltage Setpoints Amendment 19 of the technical specifications included identified improvements and was issued by NRC.

g ~

Evaluation of Amber Warning Lights on Control Panels The NSAG review was completed as discussed in inspection report 85-32.

However, the NSAG, Compliance, or POC action item tracking systems did not include this item to assure resolution of the issues identified by NSAG.

Only one of the three principal NSAG recommendations had been implemented (preparation of procedure review guidelines to address amber lights in future procedure reviews).

The other items (removal of unnecessary lights and revision of annunciator or other procedures to address existing lights) had not been implemented or resolved.

Disposition of these items will be reviewed during a future inspection.

(86-06-05)

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Management Objectives With regard to the three objectives identified in section IV of the attachment to inspection report 85-09, Supply System management representatives and the plant manager noted the following specific initiatives:

(1)

Transition to a Mature Operating Organization Continui'ng emphasis was placed on strengthening the operations leadership and further orienting of the support staff.

At the corporate level, the electrical production mission of the Supply System was highlighted through the position title of A'ssistant Managing Director for Operations.

Also, broader budget approval author'ity was given to the Operations Department.'n response to a consultant's recommendation, the Office of the Assistant Managing Director for Operations was moved to the Headquarters suite of the Managing Director.

At the plant level increased priority wa's given to maintenance and engineering matters identified by the operations staff.

Plant.

operations crews were given lead responsibility for revising operating procedures.

(2)

Build on Identified Strengths and Improve Areas of Weakness Specific strengths/weaknesses to be addressed in the context of the enforcement conference presentation had not been defined.

However, the plant manager pointed to the heavy involvement of the staff in owners'roup, INPO and other internal and external audit activities as evidence of the Supply System commitment to continuing improvements.

(3)

Improve Working Relationship with Regulatory Agencies The licensee reinforced the Compliance Engineer position and established computer tracking systems for external commitments.

The activities of the Compliance Engineer were more clearly directed to identify concerns raised by the NRC and improve communications relating to such items.

Also, a Technical Specifications interpretation procedure was implemented to assure clear definition of methods of implementing Technical Specifications requirements.

The licensee had developed several channels of communication with NRC offices and staff and was utilizing these freely to identify acceptable approaches prior to submitting formal proposals.

Improved Communications Effort In the Supply System's response to the Notice of Violation which resulted from inspection report 85-09, the licensee committed to improving communications between different groups of the plant staff, and maintaining an active management involvement.

The inspector has observed several management initiatives with respect

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to these two items and noted continuing management dialogue on these subjects:

(1)

Plant Managers (Assistant Plant Manager, Maintenance Manager, Outage Manager), technical staff engineers, engineering staff engineers, NSAG engineers, and QA engineers participated in licensed operator 'training programs, offering opportunity for improving personal communications among such personnel.

(2)

A rotation program was informally implemented to bring technical/engineering/operations personnel into different assignments.

(3)

The assistant plant manager was actively attending department safety meetings to increase direct communications with line personnel.

(4)

An assistant operations manager position was created, staffed with an experienced SRO/Shift manager, with emphasis on montioring daily operations problems and conveying instructions to other departments.

(5)

The "One Minute Manager" video tape was offered to all department managers as an element toward improving communications.

(6)

The Assistant Plant Manager assumed personal responsibility for preparation of the daily status report, which is distributed to all site and corporate departments, to elevate the status of the report and provide additional opportunity for communication with plant and corporate staff.

The inspector concluded that the licensee had generally implemented the policies and principles described to NRC at the February l985 enforcement conference, without benefit of formal action plans and specific item tracking in each case.

No violations or deviations were identified.

12.

Mana ement Meetin During this period the inspectors met with the Plant Manager weekly to discuss the status of inspection findings.

On February 28, 1986, the inspectors met with the'ssistant Managing Director for Operations, the Plant Manager, and members of his staff to discuss the inspecton findings identified during this period.

The violation regarding improper securing of a nitrogen bottle to a safety-related line was noted.

The Plant Manager indicated that the equipment qualification training committed to in the Supply System response to the notice of violation letter dated December 19, 1985, would be completed by April 1, 198 H

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