IR 05000395/1988010

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Insp Rept 50-395/88-10 in Apr 1988.No Violations Noted. Major Areas Inspected:Previous Insp Findings,Monthly Surveillance Observations,Monthly Maint Observations & Operational Safety Verification
ML20154P863
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 05/13/1988
From: Dance H, Hopkins P, Modenos L, Prevatte R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20154P851 List:
References
50-395-88-10, NUDOCS 8806060100
Download: ML20154P863 (8)


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50 080 UNITED STATES

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NUCLEAR REGULATORY COMMISSION REGION 11

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Report No.:

50-395/88-10

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Licensee:

South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.:

50-395 License No.:

HPF-12 Facility Name:

V, C. Summer Inspection Condu ted:

April 1- 0, 1938

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Inspect rs:

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& rev&tteAUw c'lahr Date Signed Perr. C. HopKins Date Signed A

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Leof Modenos (Apr 1 25-29, 1988)

Dat Signed Approved by:

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'Hugh Cv Dance, Section Chief Uate Signed DivisionofReactorProjects

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SUMMARY Scope:

This routine, announced inspection was conducted on site by the resident inspectors in the areas of ifcensee action on previous inspection

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findings, monthly surveillance observations, monthly maintenance observation, operational safety verification, engineered safety features system walkdown, onsite followup of sverits and subsequent written reports, onsite review committee, and other arer, Results:

One violation was identified in the area of inadequate compensatory action for inoperable fire protection equipment.

8806060100 esos16 PDR ADOCK 05000395 Q

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REFORT DETAILS 1.

Persons Contacted Licensee Employees D. Nauman, Vice President, Nuclear Operations

  • 0. Bradham, Director, Nuclear Plant Operations

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D. Moore, General Manager, Engineering Services

  • M. Williams, General Manager, Nuclear Services
  • K. Nettles, General Manager, Nuclear Safety J. Skolds, General Manager, Station Operations
  • M. Browne, General Manager, Station Support G. Hoffatt, Manager, Maintenance Services
  • G. Soult, Manager, Operations
  • A. Koon, Manager, Nuclear Licensing C. Bowman, Manager, Scheduling and Modifications K. Woodward, Manager,. Nuclear Operations Education and Training
  • W. Baehr, Manager, Chemistry and Health Physics S. Hunt, Manager, Quality Systems
  • K. Beale, Manager, Nuclear Protection Services C. Price, Manager, Technical Oversite D. Warner, M eager, Core Engineering and Nuclear Computer Services J. Shepp, Associate Manager, Operations W. Higgins, Supervisor, Regulatory Compliance NRC Resident Inspectors
  • R. Prev::tte, Senior Resident Inspector
  • P. Hopkins, Resident Inspector Other licensee employees contacted included engineers, technicians, operators, mechanics, security force members, and office personnel.
  • Attended exit interview 2.

Exit Interview (30703)

The inspection scope and findings were summarized on May 2, -1988, with

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those persons indicated in paragraph 1 above.

The inspectors described the areas inspected and discussed the inspection findings.

The licensee acknowledged the violation described in paragraph 6.c. and the licensee identified violation in paragraph 6.b.

The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during the inspection.

3.

Licensee Action on Previous Inspection Findings (92701, 92702)

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(Closed)

Violation 87-20-01, Failure to provide design input for modifications.

The licensee provided a written response to this violation in a letter to Region II, dated October 21, 1987.

The inspector reviewed the licensee's responses and the corrective actions taken to prevent

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recurrence.

These actions included training for the engineers, responsible for the design inputs, to ensure that they can more effectively implement the requirements contained in the established procedures.

The inspector verified the training records.

This item is closed.

(Closed)

Violation 87-20-02, Inadequate design analysis which lead to exceeding a Technical Specification (TS) room temperature limit.

The licensee has made a change to the modification program which provides for a more thorough justification and implementation of design changes.

The licensee has also requested a TS change to raise the maximum allowable pump room temperature to a value which more realistically :eflects the equipment qualification requirements for that room.

This item is closed.

(Closed)

Violation 87-20-03, failure to operate in accordance with procedures in that flow was not maintained as required and the procedures did not contain manufacturers precautions.

The licensee reviewed and verified the values designated in System Operating Procedures (50P) 117 to be correct.

However, the operating trend logs had to be changed to reflect the values of S0P 117.

The licensee revised 50P 117 to include the motor restart requirements in the precaution section of the procedure.

The inspector verified the changes to 50P 117 and operating logs.

This item is closed.

(Closed) Violation 87-20-04, Inadequate review of previous audit findings for adequacy of corrective action implementation.

The licensee revised Quality Assurance Procedures to describe the necessary evaluations and documentation which will be required to assure that previous audit findings are given proper attention.

The inspector reviewed Quality and Procurement Services Procedures (QPS-10) audit / surveillance report preparation and confirmed the changes have been made.

This item is closed.

(Closed)

Unresolved Item 86-18-01, VT-2 eye examination.

This item concerns the eye examinations given to operations personnel performing VT-2 examinations in accordance with ASME Boiler and Pressure Vessel (ASME B & PV) Code Section XI.

The item concerned the equivalency of the SCE&G eye test with that specified in ASME B & PV Section XI.

To avoid any questions, the licensee has committed to retesting all operations VT-2 examination personnel with a test identical to that specified by ASME B &

PV Section XI.

As a follow up to Inspection Report 50-395/87-25, all but 14 examiners had been tested and found optically qualified to perform VT-2 examinations.

Since then, the licensee has completed testing the remaining 14 VT-2 examiners and all were found to be optically qualified to perform VT-2 examinations.

This item is closed.

4.

Monthly Surveillance Observation (61726)

The inspectors observed surveillance activities of safety related systems and components to ascertain that these activities were conducted in accordance with license requirements.

The inspectors observed portions of

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41 selected surveillance tests including all aspects of Solid State Protection System Actuation Logic and Master Relay Test for train "B",

(STP 345.074).

The inspectors also verified that required administrative approvals were obtained prior to initiating the test, testing was accomplished by qualified personnel, required test instrumentation was properly calibrated, data met TS requirements, test discrepancies were rectified, and the systems were properly returned to service.

No violations or deviations were identified.

5.

Monthly Maintenance Observation (62703)

The inspectors observed maintenance activities of safety related systems and components to ascertain that these activities were conducted in accordance with approved procedures, TS and appropriate industry codes and standards.

The inspectors also determined that the procedures used were adequate to control the activity, and that these activities were accomplished by cualified personnel.

The inspectors independently verified that equ pment was properly tested before being returned to service.

Additionally, the inspectors reviewed several outstanding job orders to determine inat the licensee was giving priority to safety related maintenance and a backlog which might affect its performance was not developing on a given system.

The following specific maintenance

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activities were observed:

WR 213690002 Fabricate and install supports for MRF 21369 WR 8610456 Repair subpanel X26F so that it can be tested from test push buttons WR 880442 Investigate / repair digital rod position indication cooling water malfunction WR 88044 Repair ruptured diaphragm on reactor make up water valve XUD019148 WR 317450015 Determinate, remove and reinstall

"B" component cooling water pump motor for MRF 31745 PMTS P0101925 Lubricate valve XVG010378-0-EF service water header "B" cross current isolation valve MWR 214100002 Terminate cables and perform post modification testing for temporary MRF 21410 WR ?800453 Investigate and repair oil leak on inboard bearing for "A" reactor building spray pump PMTS 101743 Inspect 7.2 kV switchgear breaker WR 88I0095 Inspect and repair reactor trip breaker XSW1001-RTA

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PMTS P009601 Perform inspection and operational test on the HVAC system water chiller (XHC0010)

WR 8800465 Trouble shoot and repair valve operator / operating circuit for steam generator ' A" blow down control valves WR 8800497 Investigate and repair chilled water system valve XVT 06384-A WR 8800506 Investigate and repair service water valve (3110A)

PMTS P0101797 Engineered safety features switchgear room ambient temperature switch verification WR 8800510 Repair service water valve for the "A" diesel WR 88E0062 Perform individual cell charging on cells 16 thru 30 of battery 1A WR 8810115 Relug "A" train lamp wiring - HVAC WR 213720001 Fabricate and install supports No violations or deviations were identified.

6.

Operational Safety Verification (71707)

a.

The inspectors toured the control room, reviewed plant logs, records and held discussions with plant staff personnel to verify that the plant was being operated safely and in conformance with applicable requirements.

Specific items inspected in the control room included:

adequacy of staffing and attentiveness of control room personnel, TS and procedural adherence, operability of equipment and indicated control room status, control room logs, tagout books, operating orders, jumper / bypass controls, computer printouts and annunciators.

Tours of other plant areas were conducted to verify equipment operability, control of ignition sources and combustible materials, the condition of fire detection and extinguishing equipment, the control of maintenance and surveillance activities in progress, the implementation of radiation protective controls and the physical security plan.

Tours were conducted during normal and random off hour periods.

b.

On April 8,1988 at 2:00 p.m., with the plant in mode 1,100% power, the licensee identified two unsealed core drills.

The unsealed 2" core drills contained 1 1/2" diameter lighting conduit that penetrated the north wall of the control building at the 422 foot elevation.

The two core drills were installed under field change

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request 8-13, 855C on October 8,1981, were inspected by Quality Control, and are listed on the E412 plant drawings.

These penetrations should have been sealed under the Bisco Program when the conduits were installed.

The modifications group identified this problem on April 8,1988.

They notified operations who immediately initiated a priority 1

maintenance work request.

Non-conformance notice 2946 was written and the penetrations were sealed with 5" of foam on April 18, 1988, in accordance with detail "A" in drawing E-201-240 and approved site procedures.

Further inspections identified no other unsealed penetrations.

The failure to identify this problem is contrary to the requirements of Quality Control inspection procedures and the licensee fire protection arogram.

The NRC wishes to encourage and support licensee initiatives for self-identification and prompt correction of problems.

Since this item meets the applicable guidance of NRC enforcement policies for licensee identified items, contained in 10 CFR 2, Appendix "C", no violation will be issued.

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The licensee is currently preparing a LER for submission on this item.

c.

On April 26, 1988, at approximately 5:35 a.m. with the plant in Mode 1, operations personnel tagged out the Fire Service CO2 System in The Relay Room, in order to perform a Surveillance Test Procedure (STP)

128.331.

TS 3.7.9.3, relay room, requires that with the low pressure CO system inoperable, within one hour establish a continuous fire

watch with backup fire suppression equipment.

The licensee discovered the discrepancy at 7:28 a.m. and then established the continuous fire watch with backup fire suppression equipment.

The failure to establish a continuous fire watch within the hour as described above is a violation, "Failure to take adequate compensatory action for inoperable fire protection equipment",

50-395/88-10-01.

Although, the licensee identified the violation and took prompt corrective action, this is a repetitive event.

A similar violation was identified in Inspection Report No. 50-395/87-24.

One violation was identified as discussed in paragraph c. above.

7.

ESF System Walkdown (71710)

The inspectors performed a walkdown of the Emergency Operoting Procedure for Control Room Evacuation (EOP-8) and the General Operating Procedure for plant shutdown from hot standby to cold shutdown with the control room inaccessible (GOP-8).

All emergency tool kits were inventoried and all local station procedures were verified to be control copies of the latest revision.

The inspectors verified that equipment listed in the procedures were identified with labels and that a licensed operator was able to locate all components and equipment.

A listing of minor procedural

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deficiencies, missing tags and labels, and suggested human factors improvements were provided to the licensee for correction.

The inspectors will verify in subsequent inspections that these items are corrected.

The inspectors noted that these were lengthy procedures that require good coordination and team work to successfully accomplish under actual conditions.

These procedures are covered in classroom as part of the requalification training program, however, no actual plant walk thru's are sci.eduled or required for these events.

In view of the above it was suggested that the licensee evaluate the present training conducted in this area.

No violations or deviations were identified.

8.

Onsite Followup of Events and Subsequent Written Reports (92700,93702)

The ins)ectors reviewed the following Licensee Event Report (LER) to ascertain whether the licensee's review, corrective action and resort of

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the identified event or deficiency was in conformance with regu atory requirements, TS, license conditions, and licensee procedures and controls.

Based upon this review the following items are closed.

LER 87-18 Fire protection surveillance non-compliance; personnel error and lack of procedural guidance No violations or deviations were identified.

9.

Onsite Review Committee (40700)

The inspectors reviewed the licensee's program for the Onsite Review Committee to verify that it met the requirements of TS Section 6.5, the Final Safety Analysis Report (FSAR) and the licensee's Quality Assurance Plan.

The requirements of the above are implemented by the licensee in Station Administrative Procedure, Plant Safety Review Committee (SAP 120).

In addition, to the above, the inspectors reviewed the minutes of the last 6 Plant Safety Review Committee (PSRC) meetings,10 recent off-normal

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occurrences, 15 plant administrative procedures, a sampling of TS violations for the past year, the lifted lead jumper and bypass authorization log, and attended the PSRC meeting conducted on April 20, 1988 to verify that this committee was fulfilling the requirements of TS and other stated commitments.

Their review indicated that plant off-normal events which have safety significance are reviewed by the PSRC to fnsure that immediate corrective action is implemented to place the plant in a safe condition, that the root cause is determined, the event is reported if required and that long term corrective action is taken to prevent recurrence.

Attendance of the PSRC meeting and a review of the minutes of past meetings indicate that a quorum is present at meetings and i

that the PSRC reviews changes to the security and emergency plan, plant modifications, non-conformances, off-normal occurrences, and procedural

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changes, which involve an unreviewed safety question, are reviewed by this committee.

This review also noted that although TS requires this committee to meet once per calendar month, it routinely meets at least once per week and after the occurrence of a plant trip or significant event.

No violations or deviations were identified.

10. Other Areas a.

The inspectors attended the licensee's annual presentation for the V.

C. Summer Plant to the Board of Directors for South Carolina Electric and Gas Company (SCE&G) and the South Carolina Public Service Authority on April 15, 1988 at the SCE&G corporate office in Columbia, S.C.

b.

The senior resident inspector served as the backup resident inspector at the H. B. Robinson Plant while the assigned resident inspectors were absent during the week of April 25, 1988.

c.

The Region II Project Engineer for the V. C. Summer Plant served as the backup resident inspector for the week of April 25, 1988 during the absence of the assigned resident inspectors.

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