IR 05000400/1986091

Insp Rept 50-400/86-91 on 861120-1220.No Violation or Deviation Noted.Major Areas Inspected:Status of TMI Action Items,Licensee Action on Previous Enforcement Matters, Unresolved Items & Tech Specs Verification

ML20210K079
Person / Time
Site:	Harris
Issue date:	01/13/1987
From:	Burris S, Fredrickson P, Maxwell G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20210J943	List: IR 05000400/1986091 ML20210J940
References
TASK-1.D.1, TASK-2.D.1, TASK-2.E.4.2, TASK-TM 50-400-86-91, NUDOCS 8702120188
Download: ML20210K079 (6)

Text

._

.

UNITED STATES f .pt Wuq*o NUCLEAR REGULATORY COMMISSION

[ n REGloN ll

$ j 101 MARIETTA STREET, '* I

'* ATLANTA, GEORGI A 30323

\...../

Report No.: 50-400/91 Licensee: Carolina Power and Light Company P. O. Box 1551 Raleigh, NC 27602 Docket No.: 50-400 License No.: NPF-53 Facility Name: Harris 1

Inspection r nductedJ November 20 - December 20, 1986 Inspectors:( . Ifl2 fM Q F. Maxwf 1 .Date Signed k* A i I I" $ P. Burris Date Signed Approved by: 7" / /3/[7 P. 'E. Fredrickson, Section Chief 7 ate S'igned Division of Reactor Projects SUMMARY Scope: This routine, announced inspection involved inspection in the areas of Status of Three Mile Island Action Items, Licensee Action on Previous Enforcement Matters and Unresolved Items, Maintenance Observation, Technical Specifications Verification, Onsite Review Committee, Review of Nonconformance Reports, and Other Activitie Results: No violations or deviations were identifie PDR ADOCK 05000400 0 PDR

- _ -

-

.

REPORT DETAILS Persons Contacted Licensee Employees J. M. Collins, Manager, Operations G. L. Forehand, Director, QA/QC J. L. Harness, Assistant Plant General Manager, Operations C. S. Hinnant, Manager, Start-up

-

L. I. Loflin, Manager, Harris Plant Engineering Support C. H. Moseley, Manager Operations QA/QC G. A. Myer, General Manager, Milestone Completion M. F. Thompson, Jr. , Manager, Engineering Management D. L. Tibbitts, Director, Regulatory Compliance R. B. Van Metre, Manager, Harris Plant Maintenance R. A. Watson, Vice President, Harris Nuclear Project J. L. Willis, Plant General Manager, Operations Other licensee employees contacted included construction craftsmen, technicians, operators, mechanics, security force members, engineering personnel and office personne . Exit Interview The inspection scope and findings were summarized on December 19, 1986, with the Plant General Manager, Operations. No written material was provided to the licensee by the resident inspectors during this reporting period. The licensee did not identify as proprietary any of the materials provided to or reviewed by the resident inspectors during this inspectio . Status of Three Mile Island Action Items (25401B) (Closed) Inspector Follow-up Item 400/85-16-06, Three Mile Island Item I.D.1 " Control Room Design Review." Section 18.1 of Supplement 4 to the SER summarizes the status of this item. Supplement 4 indicates that a license condition will require the licensee to provide the final results of the control room survey before start-up, following the first refueling. For tracking purposes, the inspectors determined that there is no need for this item to remain open. This item is close (Closed) Inspector Follow-up Item 400/85-16-11, Three Mile Island Item II.D.1 " Performance Testing of Boiling Water Reactor and Pressurized Water Reactor Relief and Safety Valves." The inspectors reviewed

_ .__

_.

_

, . 2

, _

.

CP&L's responses. submitted June 28, 1984, June 6, 1986 and July 3,

1986,. . which contained information from Electric Power =Research Institute valve test program and results which apply to Shearon Harris-Uni t .1'. These submittals described the full-scale valve ' test program and results which~ demonstrated the safety valves, power operated relief valves (PORV) and PORV block valves to be functionally operable. Base on NRR preliminary review acceptance of the licensee's submittals as-identified -in -the. Harris Safety Evaluation Report, Supplement 4, -

.Section 3.9.3, this item is-close .(Closed) Inspector Follow-up Item 400/85-16-14, Three Mile Island Item

'II.E.4.2 " Containment Isolation Dependability." To insure conformance to all of the acceptance criteria contained in 6.2.4 of NRC's Standard Review' Plan, the --inspectors reviewed the information in the - Final Safety' Analysis Report, Safety Evaluation Report and responses' by the licensee to NRC questions concerning the containment isolation . syste Based on' Nuclear Reactor Regulation's acceptance of the submitted

' Technical Specificatio'ns, . the questions identified in the Shearon Harris SER have been addressed. This item is close (Closed) Inspector Follow-up Item 400/85-16-27, Three Mile' Island Item III.D.1.1 " Integrity of Systems Outside Containment Likely to Contain Radioactive Materials." The licensee has established the requirements for a leak reduction program. The requirements are outlined in Section 6.8.4 of the operations Technical Specifications and are implemented by si te' ' procedure s titled " Inservice Gas Systems Leakage Inspection" (EPT-013T) and " Inservice Liquid System Leakage Examination (EPT-220)."

The inspectors interviewed. the responsible licensee personnel and evaluated 18 marked up drawings and associated documents which outlined those systems which. have been inspected and tested as required by EPT-013T and EPT-220. The inspectors determined that the licensee has implemented the procedures which assure the integrity of the ' plant systems outside the containment that are likely to contain radioactive material. This item is close . Licensee Action on Previous Enforcement Matters and Unresolved Items (92701, 92702) .(Closed) Violation 400/86-60-01, " Failure to Reflect the As-Built Condition on System Configuration Drawings." The inspectors reviewed the corrections made to the identified drawings and found that the licensee's engineering section had correctly implemented these change The inspectors reviewed several other design changes to drawings and found that these changes had been reviewed and correctly incorporated by the engineering section. This item is close .

3 (Closed) Unresolved Item 400/86-80-02, " Design Control." The inspec-tors reviewed recent changes to the Auxiliary Feedwater System, Fire Protection Water Supply System and Chemical and Volume Control System drawings. They verified that these changes were based on appropriate design change or modification procedures, documentation review by tha appropriate engineering personnel, and that incorporation of changes or modifications to field-installed equipment was performed correctl The inspectors found-that these actions were accomplished in accordance with an approved design engineering program. This item is close . Maietenance Observation (92719)

The inspectors observed maintenance activities and reviewed records to verify that work was conducted in accordance with approved procedures, Technical Specifications, and applicable industry codes and standards. The inspectors also verified the following: redundant components were operable, when required; administrative controls were followed; tagouts were adequate; personnel were qualified; correct replacement parts were used; radiological controls were proper; fire protection was adequate; quality control hold points were adequate and observed; adequate post-maintenance testing was performed; and independent verification requirements were implemented. The inspectors independently verified that selected equipment was properly returned to service. Outstanding work requests were reviewed to insure that the licensee gave priority to safety-related maintenanc The inspectors observed and reviewed portions of the following maintenance activities:

-

MST-E-0010, 1E battery weekly test;

-

MST-I-0042, refueling water storage tank liquid level channel III calibration;

-

MST-I-0006, containment pressure protection set;

-

MST-I-0029, steam generator 3C narrow range level detectors;

-

MST-I-0083, steam generator "A" wide range level loop;

-

MST-I-0178, component cooling surge tank protectio The inspectors verified that any discrepancies found during these tests were identified and documented for proper dispositio No violations or deviations were identifie . Technical Specifications Verification (71501C)

The inspectors verified conformance with Technical Specifications require-ments by direct observations or activities, facility tours, discussions with personnel, reviewing of records and independent verification of safety system statu _ _

-

.

The' inspectors verified that control room manning requirements of 10 CFR 50.54 and the Technical Specifications were me Control room, shift supervisor, and clearance logs were reviewed to obtain information con-cerning operating trends and out of service safety systems to insure .that there were no conflicts with Technical Specifications Limiting Conditions for Operations. Direct observations were conducted of control room panels, instrumentation and recorder traces important to safety to verify operabil-ity and that parameters were within Technical Specifications limits. The inspectors observed shift turnovers to verify that continuity <of system status was maintained. The inspectors verified the status of selected control room annunciator The inspectors verified that the licensee's health physics policies and procedures were followed. This included a review of area surveys, radiation work permits, posting, and instrument calibratio The inspectors verified the following: the security organization was properly manned and security personnel were capable of performing their assigned functions; persons and packages were checked prior to entry into the protected area (PA); vehicles were p.roperly authorized, searched and escorted within the PA; persons within the PA displayed photo identification badges; personnel in vital areas were authorized; and effective compensatory measures were employed when reo,uire The inspectors also observed plant housekeeping controls, verified position of certain containment isolation valves, and verified the operability of onsite and offsite emergency power source No violations or deviations were identifie . On site Review Committee (71501C)

The inspectors reviewed Plant Nuclear Safety Committee (PNSC) meetings 86-27 and 86-28 on December 2 and 4, 1986, respectively, concerning changes to Technical Specifications which are currently proposed to NRC. The inspec-tors verified that these meetings were conducted in accordance with TS requirements regarding membership, quorum, review process, frequency and member / alternate qualification The inspectors reviewed the meeting attendance list to insure that those individuals designated as alternates were on the required administrative list and were qualified to hold that positio The inspectors reviewed these proposed changes to ascertain if the PNSC's evaluation process was performed in accordance with applicable 10CFR 50 guidelines, Technical Specifications and licensee-approved procedure Although similar changes to other licensee's Technical Specifications had been reviewed and approved by NRC, the inspectors questioned the method for revising Procedure PLP-106 since these valves were identified in Technical Specification Licensing personnel pointed out that Procedure PLP-106 required PNSC review prior to any changes to the procedure, and in addition, quarterly 10 CFR 50.59 submittals for a period of two years would be made,

. - . .. . _ - - -, - ---- - _ _ -

---

V -

'

. . . >

then annually thereafte The inspectors will continue to monitor th status of these submittals during future inspection period No violations or deviations were identified in the areas inspecte . Review of Nonconformance Reports (71501C)

During this inspection period the inspectors reviewed Nonconformance Reports (NCRs) nd Quality Assurance Surveillance Reports (QASRs). The inspectors conducted this review by direct observation of selected Quality Assurance activities, review of the documentation, and interviews with QA, operations and maintenance personne The inspectors reviewed approximately 90 NCRs and QASRs to insure that the licensee's program addressed the proper imple-mentation of the site-approved procedures to control the following:

-

Adequate identification of the specific problem for each of the non-conforming conditions;

-

Detailed corrective action and disposition of tne nonconforming con-dition;

-

Verification of the corrective actions by the appropriate level of licensee management, with acceptance or rejection of the disposition, as required;

-

Reinspection of the corrected nonconforming condition, if required;

-

Final reviews and closecut of these nonconformances was performed in accordance with approved site procedure The inspectors concluded that these activities were performed in accordance with all applicable guidance and requirement No violations or deviations were identifie . Other Activities (92719)

On December 18, 1986, the Director of Nuclear Reactor Regulation visited the Harris Plant. He attended a public presentation where CP&L provided the status of operator training, INP0 training program, operational readiness, construction, plant staffing, preoperational testing, start-up, maintenance, the unique plant features, general configuration of the site and the plant capacity. Members representing parties to the license hearing attended the CP&L presentation and accompanied the Director for the duration of his visi A plant tour followed the CP&L presentation. The tour included stops in the turbine building near the feedwater pumps, the diesel generator building, the main control room, the high voltage switchgear room, portions of the reactor auxiliary building, the fuel handling building and the waste process building control room. After completing the tour, an exit meeting was held between NRC and CP&L management.