IR 05000321/1987019

Insp Repts 50-321/87-19 & 50-366/87-19 on 870704-31. Violation Noted.Major Areas Inspected:Licensee Action on Previous Enforcement Matters,Maint Observation,Radiological Protection,Physical Security,Ros & General Training

ML20237K668
Person / Time
Site:	Hatch
Issue date:	08/14/1987
From:	Holmesray P, Menning J, Randy Musser, Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20237K659	List: IR 05000321/1987019 ML20237K657 ML20237K661
References
50-321-87-19, 50-366-87-19, NUDOCS 8708270249
Download: ML20237K668 (8)

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o UNITED STATES 8' n NUCLEAR REGULATORY COMMISSION

$ E REGION l!

o, 101 MARIETTA ST., N.W., SUITE 3100

,o b[ ATLANTA, GEORGI A 30303

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Report Numbers: 50-321/87-19 and 50-366/87-19 Licensee: Georgia Power Company P.O. Box 4545 Atlanta, GA 30302 Docket Numbers: 50-321 and 50-366 License Numbers: DPR-57 and NPF-5 Facility Name: Hatch 1 and 2 Inspection Dates: July 4-31, 1987 Inspection at Hatch site near 8axley, Georgia Inspectors:  % -

4/// $7 D(te Signed Peter Holmes-Ray, Sprrior Resident Inspercor NND Jo enning, sident Inspector Dat'e ' Signed

'$ & $ll4l81 Randall A. Musser, Resident Inspector Da'te Signed

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Approved by: /

Marvin V. Sinkule, Chief, Project Section 2C Date Signed Division of Reactor Projects SUMMARY Scope: This routine inspection was conducted at the site in the areas of Licensee Action on Previous Enforcement Matters, Operational Safety Verification, Maintenance Observation, Plant Modification and Surveillance Observation, Radiological Protection, Physical Security, Reportable Occurrences, and General Employee Trainin ,

Results: One violation was identifie PDR ADOCK 05000321 Q PDR _ _ _ . _ - _ _ _ _ _ _ - _ _ -_

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REPORT DETAILS Persons Contacted Licensee Employees

• T. Beckham,.Vice President, Plant Hatch

• H.C. Nix, Plant Manager

• D. Read, Plant Support Manager

• H.L. Sumner, Operations Manager

• P.E. Fornel, Maintenance Manager

• T.R. Powers, Engineering Manager

• R.W. Zavadoski, Health Physics and Chemistry Manager

• C. Coggin, General Support Manager M. Googe, Outages and Planning Manager

• 0.M. Fraser, Site' Quality Assurance (QA) Manager

• C.T. Moore, Training Manager

• S.B. Tipps, Superintendent of Regulatory Compliance Other licensee employees contacted included technicians, . operators,

-: mechanics, security force members and office personne * Attended exit interview Exit Interview (30703)

The inspection scope and findings were summarized on July 31, 1987, with those persons indicated in paragraph I abov The licensee did not identify as proprietary any of the material provided.to or reviewed by the inspector (s) during this inspectio The licensee acknowledged the findings and took no exceptio (0 pen) Violation 50-321/87-19-0 Inadequate maintenance procedur (Paragraph 5) Licensee Action on Previous Enforcement Matters (92702)

(Closed) Violation 321, 366/85-09-01, Failure to Establish Procedures for Required Technical Specifications (T.S) Temperature Monitoring and Recording.GPC letter of May 29,1985 was reviewed. The immediate actions taken were adequate to provide the proper monitoring and recording of the temperatures in questio The licensee has tied the closing of this violation to. Quality Assurance item QA-85-SURV-1/89,"Two examples were identified where the Hatch T.S. surveillance program missed the required frequency for performance." Corrective action for the QA item entails completing the procedures upgrade program (PUP), which includes a line-b line review of T.S. vs issued instruction The PUP has a 12-31-88 completion schedule. Since the actions to correct the specifics of this

> violation have been completed, this item is close The PUP is being followed by the resident inspectors.

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(Closed) Violation 321/85-09-02, Pressure-Temperature Curves Were Not Corrected for Fluence. The GPC letter of May 29, 1985 was reviewed.- l Adequate corrective actions were taken including changing the T.S. to )

include revised curves. This item is close (Closed) Unresloved Item 321/86-25-01, Improper Assembly of Refueling Floor to Standby Gas Treatment System Suction Dampers. Special purpose procedure 42SP-062387-0P-1-15 was ' performed and showed that the required negative pressure could be obtained with the dampers in the as found condition. There are two trains feeding into a single suction line such ,

that if either suction damper is open the running train has a suction {

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path. The length of time the dampers were improperly operating is indeterminate. In January 1983 EQ modifications were made to the system i and miswiring could.have taken place at that time. The damper wiring has been corrected. This item is close . Operational Safety Verification (71707)

The inspectors kept themselves informed on a daily basis of the overall plant status and any significant safety matters related to plant operations. Daily discussions were held with plant management and various members of the plant operating staff. The inspectors made frequent visits to the control room. Observations included instrument readings, setpoints and recordings, status of operating systems, tags and clearances on equipment, controls and switches, annunciator ' alarms, adherence to limiting conditions for operation, temporary alterations in effect, daily journals -and data sheet entries, control room manning, and access controls. This inspection activity included numerous informal discussions with operators and their supervisor Weekly, when on si te, selected Engineering Safety Feature (ESF) systems were confirmed operable. The confirmation was made by verifying the following: accessible valve flow path alignment, power supply breaker and fuse status, instrumentation, major component leakage, lubrication, cooling, and general conditio On July 16, 1987, while walking down the Unit 2 "A" core spray system loop, the inspector noted an inconsistency between the as-found condition of a valve and the licensee's valve lineup sheets for the system. .The system valve lineup is included as Attachment 3 to procedure 34S0-E21-001-2S, " Core Spray System". The currently specified lineup requires condensate supply drain valve 2P11-F036A to be in the closed positio The inspector found this valve to be locked close Discussions with operations personnel revealed that the licensee had '

previously identified this inconsistency and intends to require the valve to be locked closed in an upcoming revision of 34S0-E21-001-2S. The inspector will review this revision when issue During the walkdown of the Unit 2 "A" core spray system loop, the inspector also noted that six valves were not tagged with the Master Parts List (MPL) numbers that are i 4

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used to identify these valves in the valve lineup sheets. Operations personnel indicated that they had already identified the need to tag these valves with their MPL numbers and intended to do so. The inspector subsequently confirmed that the six valves had been tagged with their MPL number General plant tours were conducted on at least a weekly basis. Portions of the control building, turbine building, reactor building, and outside areas were visite Observations included general plant / equipment ,

conditions, safety related tagout verifications, shift turnover, sampling program, housekeeping and general plant conditions, fire protection equipment, control of activities in progress, radiation protection controls, physical security, problem identification systems, missile hazards, instrumentation and alarms in the control room, and containment isolatio No violations or deviations were identifie . Maintenance Observation (62703)

During the report period, the inspector (s) observed selected maintenance activities. The observations included a review of the work documents for adequacy, adherence to procedure, proper tagouts, adherence to technical specifications, radiological controls, observation of all or part of the actual work and/or retesting in progress, specified retest requirements, and adherence to the appropriate quality control During the 1987 Unit 1 outage the licensee failed to provide adequate procedures for the repair of the Local Power Range Monitoring (LPRM)

system. The procedure step that detailed the connection of the cable (s)

to the detector (s) called for the verification and hookup of each detector cable in sequence for A, B, C and D detector in a given string. The data package contained a single verification for each string vs each individual connection. This difference led to ten LPRM cables improperly connecte On June 28, 1987 the improper hookup was confirmed and corrected. The ,

other LPRM strings were verified to be correctly assemble This '

inadequate procedure is a violation to be tracked as 50-321/87-19-0 . Surveillance Testing Observations (61726)

The inspector (s) observed the performance of selected surveillance. The observation included a review of the procedure for technical adequacy, I conformance to Technical Specifications, verification of test instrument ,

calibration, observation of all or part of the actual surveillance, j removal from service and return to service of the system or components j affected, and review of the data for acceptability based upon the I acceptance criteri No violations or deviations were identifie I I

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1 ESF System Walkdown (71710)

The inspectors routinely conducted partial walkdowns of ESF systems. Valve  :

and breaker / switch lineups and equipment conditions were randomly verified both locally and in the control room to ensure that lineups were in accordance with operability requirements and that equipment material conditions were satisfactor The Unit 1 Standby Liquid Control system was walked down in detai During this walkdown on July 23, 1987, the inspectors noted an apparent discrepancy between the requirements of the system operating procedure and the actual setting of a temperature indicating switch. The current system procedure is 34S0-C41-003-IS, Rev. 1, " Standby Liquid Control System".

Step 7.1.9 of this procedure requires verification that Suction Line Temperature Indicating Switch IC41-N007 is set at 55 F. The inspectors observed that the switch was actually set at 70 F. Although not concerned about a violation of technical specification requirements, the inspectors brought this discrepancy to the attention of operations personnel for resolution. The inspectors will follow this matte l Within the areas inspected, no violations or deviations were identifie . Radiological Protection (71709)

The resident inspectors reviewed aspects of the licensee's radiological protection program in the course of the monthly activitie The performance of health physics and other personnel was observed on various shifts to include: involvement of health physics supervision, use of radiation work permits, use of personnel monitoring equipment, control of high radiation areas, use of friskers and personal contamination monitors, and posting and labelin During this reporting period, the resident inspector also reviewed implementation of the licensee's program to maintain personnel radiation exposures as low as reasonably achievable (ALARA). Requirements for this program are currently described in procedure 60AC-HPX-009-0S, Rev 1,

"ALARA Program". The inspector initially interviewed a superintendent in the Health Physics and Chemistry Department to review the licensee's systems for making dose projections and tracking exposures, corrective actions when administrative exposure limits are exceeded, and policy on revising dose goals. The inspector determined during this interview that the licensee currently establishes ALARA goals on a departmental basi The inspector subsequently interviewed a superintendent in the Maintenance Department to determine if this individual was aware of how his group's current collective dose compares with projections, the tasks that routinely contribute most to his group's dose, and actions that have been taken to reduce dose during the conduct of these task The inspector also interviewed selected maintenance and operations personnel to access their awareness of the ALARA program and of related individual responsibi'litie _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - . __ ._ ._ . _ . _ _ _ -_ _ _ - _ _

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No violations or deviations were note . Physical Security (71881)

In the course of the monthly activities,.the resident inspectors included a review.of the licensee's physical security program. The performance of j various sh.fts' of the security force was observed in the conduct of. daily activities to include: availability of supervision, availability of armed

- response personnel, protected and vital access controls, searching of personnel, packages and vehicles, badge issuance and retrieval, escorting of visitors, patrols and compensatory post No violations or deviations were note . Reportable Occurrences (90712 & 92700)

A number of Licensee Event Reports (LERs) were reviewed for potential generic impact, to detect trends, and to determine whether corrective actions appeared appropriate. Events which were reported immediately were also reviewed as they occurred to determine that Technical Specifications were being met and the public health and safety were of utmost consideration. The following LERs are closed:

Unit 1: 86-03, 86-12, 86-19, 86-25, 86-32 and 86-36 Unit 2: 86-25, 86-32, 86-34 and 86-35 11. Operating Reactor Events (93702)

The inspectors reviewed activities associated with the below listed reactor event The review included determination of cause, safety significance, performance of personnel and systems,and corrective actio The inspectors examined instrument recordings, computer printouts, operations journal entries, scram reports and had discussions with operations maintenance and engineering support personnel as appropriat On July 23, 1987 at 9:14 pm, CDT, Unit 1 SCRAMed on low veter level. The-low water level was caused by low feedwater flow caused by loss of vital AC power. HPCI and RCIC received start signals from low-low water level HPCI functioned properly and injected to the reactor vessel. RCIC started but tripped on overspeed below the setpoint. Group 2 and 5 isolations occurred per design. A Notice of Unusual Event (NUE) was declared, as required, at 9:30 pm and terminated at 9:40 pm due to HPCI injection. The SCRAM was reset with the plant stable at 9:29 pm CDT. RCIC was repaired and Unit I was restarted on alternate vital AC at 11:33 CDT July 24, 198 The loss of vital AC inverter was caused by electrical component failure internal to the inverter.

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Dn . July 26,1987 at 2:05 pm'CDT, Unit 2 SCRAMed on low water level caused

- by? loss s of vital .' AC. . A NUE was declared at' 2:10 pm CDT due to HpCI

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injection - and was . terminated at 2:20 pm CDT. Vital AC was lost . by electrical ' component. failure internal to the inverter. A Radiological-Event was' declared at 3:16 pm CDT due to high airborne radiation levels in the Waste Gas Treatment Building. This condition.resulted when the main stack' isolation valve closed on ' loss of vital AC and 'the . subsequent j

. increase in' offgas pressure caused the loop seals in the system to be 1 lost. The Radiological Event was terminated. at 7:00 - pm CDT. The plant was stable and the scram reset at' 2:36 pm . CD All safety systems functioned as designe "

Within the' areas inspected, no violations or deviations were identifie . General. Employee Training i .

During the week of ' July 13, 1987, the new Resident Inspector at Plant f Hatch, (R. A. Musser), attended Georgia Powers General Employee  !

Training (GET). The three day course . covered the fundamentals of Health 'i Physics, Respiratory .. Protection,- Emergency and disaster . actions, and Security. The lectures and practical demonstrations were presented in a professional and easy to understand manner, and the majority of the course-was enjoyable for the student . Review of Part 21 Items P2184-01, Material supplied by Bonney Force Lacks Chemical Test - This Item is-specific to Plant Vogtle and is not applicable to

. Plant Hatch. This items is closed for Plant Hatc P2184-02, Analytical Stress Analysis Techniques for X-14 Flued Hea This item is the same as IFI 366/84-27-02. IFI 84-27-02 was closed in inspection report 50-366/87-10, therefore item P2184-02 is close P2185-01, Pipe Clamps - This is a Plant Vogtle specific item and is not applicable to Plant Hatch. This item is closed for Plant Hatc . Inspector Followup Items (92701)

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(Closed) Inspector Followup Item 321,366/87-01-01. This item involved an inspector's concern about a potential deficiency in the licensee's syste for contro111ng' the quarterly stroke time testing of power operated valves. The concern was that all of the test requirements of IWV-3410 of Section XI of the ASME Boiler and Pressure Vessel Code would not be satisfied in some cases unless quarterly testing is performed concurrently with monthly testin .

In these cases the date sheets for quarterly

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testing do not provide for all of the determinations required by Section XI. An investigation by the licensee revealed that quarterly and monthly testing have been completed at the same time every quarter. However, the licensee did determine that the technical specification surveillance data base did not reflect all of the necessary data sheet requirements in the cases of four tests. The licensee has revised this data base to reflect all' required data sheets. The inspector reviewed the licensee's followup documentation and selected data base printouts. This item is close !

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