IR 05000272/1978029

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IE Insp Repts 50-272/78-29 & 50-311/78-54 on 781217-790113. No Noncompliance Noted.Major Areas Inspected:Facility Tour, Log & Record Reviews,Followup on Previous Insp Items & Preoperational QA
ML18078A997
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/25/1979
From: Keimig R, Norrholm L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18078A994 List:
References
50-272-78-29, NUDOCS 7903140066
Download: ML18078A997 (13)
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Text

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT 50-272/78... 29 Report N /78-54 50-272 Docket N 'D:-::P'--R~-7"""'0'----

Region I c

L i c ens e No~ CPPR-53 Priority

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Category --=B'"'"l ____ _

Licensee:

Public Service Electric and Gas Company

  • 80 Park Place Newark, New Jersey 07101 Facility Name:

Salem Nuclear Generating Station - Units l and 2 Inspection at:. Hancocks Bridge, New Jersey Approved';ry LJ ~~

. R. Klii1'f9:Chief,Rtor Projects Section No. 1, RO&NS Branch Inspection Summary:

"Clate' signed date signed

. Ins ections on December 17, 1978 - Januar 13, 1979 Combined Ins ection Re art No ~272/78~29 and 50~311/78-54 Unit 1 Areas Inspected: Routine inspections by the resident inspector of plant operations including tours of the facility; log and record reviews; review of recent Licensee Event Reports; review of Monthly Operating reports; and followup on previous inspection item The inspection involved 27 inspector-hours by the resident NRC inspecto Unit 2 Areas*rnspected:

Routine inspections by the resident inspector of plant preoperational testing including tours of the facility; preoperational quality assurance; staff preoperational training; review of proposed Technical Specifi-cations; and followup on previous inspection item The inspection involved 31 pector-hours by the NRC resident inspecto ults:

No items of noncompliance were identifie Region I Form 12 (Rev. April 77)

i eos 14 ooro(O

DETAILS 1. * *Persons*contatted.. PSE&G

.

. Bar~adale, Project Construction Manager R~ Griffith, Site QA Engineer

C. Johnson, Startup Engineer S. LaBruna, Maintenarice Engineer E. Meyer, Project QA Engfoeer H. Midura, Manager - Salem Generating Station L. Mi 11 er - Performance Engineer

W. Reuther, Site QAD

F. Schnarr, Station Operating Engineer R. Silverio, Assistant to the Manager J. Stillman, Station QA Engineer W. Treston, Site QAD

J. Zupko, Chief Engineer The inspector also interviewed other licensee personnel during the course of the inspections including management, clerical, mainten-ance, operations, performance, quality assurance, testing, and construction personne Status of Previous Inspection Items (Closed) Unresolved Item (272/78-01-05):

Establishment of a system to assure that microfilm records are accurate, complete and retriev-

~ble prior to destruction of the original.. On the basis of recent inspections of retrieving records from the microfilm library and the inception of departmental and Technical Document Room procedures and practices to assure completeness of these files, this item is resolve (Closed) Unresolved Item (272/78-12-01):

Identifying marks on eme_rgency l_ight fixtures. The inspector verified by field inspec-tion that 1 ights with.. emergency power sources are now identified by means or *red marking *tap This item is resolved *

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(Closed) Unresolved Item (272/78-24-02):

Revision to Maintenance Department test procedures to record test.gage serial number The inspector reviewed a sampling of revised Maintenance Department pro-

. cedures to verify that test instrument serial numbers are now in-

  • dicated in the completed procedure. This item is resolve _(Closed) Open Item (272/78-25-02): Procedure to connect reactivity compute The inspector reviewed procedures PD-16.4-025 through-028, Connection of Power Range Drawer N41 (42-44) to Reactivity Computer for Zero Power Tes The inspector had no further ques-tions concerning this ite (Open) Follow Item (272/78-09-05): Replacement of unqualified NAMCO D2400X stem mounted limit switche The inspector noted that OCR EC-0424, which had been issued to accomplish modifica-tions dictated by IE Bulletin 78-04 did not include replacement of a number of switches which provide position indication for con-tainment isolation valve Replacement of these switches had been specified in Design Memorandum CD-M-7 A similar finding had been noted with ECN 35195 which specifies the same work on Salem Unit ECN 35294 was issued for Unit 2 on December 20, 1978 to accomplish the switch replacement and will be completed prior to core loa As stated in the licensee 1s response to IE Bulletin 78-04, the required work will be completed on Unit l during the refueling outag The inspector stated that it is expected that a similar change or supplement to the Unit 1 OCR will be made to include switch replacement on Unit 1 containment isolation valve Unit l Pl ant Tour During the course of the inspections, including backshifts, the inspector made observations and conducted tours of:

Control Room; Relay Room; Auxiliary Building:

Service Water Structure;

  • YarEI Areas; Rad Waste Building; Site Perimeter;

-- * Circulating Water Structure;,

Control Point; and,

  • Turbine Buildin The followi.ng determinations were made:

Log A sampling review of station operating logs was made to verify compliance with procedures and to verify that operating parameters~were within Technical Specifi-cation limit Monitoring instrumentation. The inspector frequently verified that selected instruments were functional and that demonstrated parameters were within Technical Speci-fication limit Valve Position The inspector verified that selected valves were in the position or condition required by the Technical Specifications for the applicable plant mod Radiation Controls..

The.inspector verified by observa-tion that control point p'rocedures and posting require-ments were being followe The inspector identified no failures to properly post radiation and high radiation area Plant housekeeping conditions. Observations relative to plant housekeep{ng and fire hazards.identified noun-satisfactory condition Fluid leak No fluid leaks were observed which had not been identified by station personnel and for which correc-tive action had not been initiated, as necessar *

Piping vibratio No excessive piping vibrations were obs~rved and no adverse conditions ~ere not~d.

I

Selected pipe hangers and seismic restraints were ob-served anc! no adverse conditions were note Control Room annunicators. Selected lit annunic~tors were discussed with control room operators to verify that the reasons for the a.l armed conditions were understood and corrective action, if required, was being take By frequent observations during the inspections, the inspector verified that the control room manning require-ments of 10 CFR 50.54(k) and the Technical Specifications were being me In addition, the inspector observed that frequent tours were made by shift supervisio The following acceptance criteria were used for the above item Technical Specifications Operations Directives Manual Inspector Judgement On January 5, 1979, a downward drift of up to 40 steps in individual rod position indication for control assembly 205 occurre Action Statement 3.1.3.2.a was implemented and con-tinued in effect at the end of this report period. The inspector verified periodically that the required flux maps were obtained at least every eight hours to ascertain rod positio Initial investigati~n indicated that the problem is inside containment poisibly, in the coil stac In the event of unit shutdown or trip, the indication anomaly must be resolved p~ior to return to operating Mod~ 2 or On January 12, 1979, inadvertent dilution of both Boric Acid Storage Tanks and the Boron Injection Tank occurred due to incomplete closure of a manual, pure water makeup valv Action Statement 3.5.4.1 became applicable and required placing the plant in HOT STANDBY within seven hour The licensee's estimate cif the batching and makeup rate indicated that restoration of the required boron concentration would take longer than the time permitted by the Action Statement.

I

Following discussions and transmittal of required information to NRC:.NRR, a facility license amendment was issued to permit, on a one-time basis, a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period prior to requiring the plant to be in HOT STANDB Boron Injection Tank boron con-centration was restored approximately ten hours prior to expiration of the time period. A Licensee Event Report will be issued detailing the even The inspector had no further questions relative to *the.plant operations observe.

Licensee Event Reports (LER's) In Office Review of Licensee Event Reports The inspector reviewed LERs submitted to the NRC:RI office to verify that details of the event were clearly reported, in-cluding the accuracy of the description of cause and adequacy of c6rrective actio The inspector determined whether further information was required from the licensee, whether generic implications were involved, and whether the event warranted onsite followu The following LERs were reviewed:

78-52/3L Containment Isolation Valve (1CC190) Inoperable 78-53/3L DNB Limit Exceeded and Reactor Critical with Tavg Less than 541°F 78-54/3L Air Particulate Detector Unit Inoperable

. *78-60/3L Inoperable Containment Personnel Airlock

  • 78-63/3L No. 13 Containment Fan Coil Unit Inoperable
  • 78-64/3L Pressurizer Pressure High Reactor Trip Above Technical Specification Limit

. 78~65/3L Containment Isolation Valve 1CC131 Inoperable

  • 78-79/3L No. 12 Steam Generator Level Channel III Inoperable Onsite Licensee Event Followup For those LERs selected for onsite followup (denoted by asterisks in detail paragraph 4.a), the inspector verified that the reporting requirements of Technical Specifications and Regulatory Guide 1.16 had been met, that appropriate corrective action had been taken, that the event was reviewed by the licensee as required by AP-4, 6, and 7, and that continued operation of the facility was conducted in accord-ance with Technical Specification limits. The following findings relate to the LERs reviewed on site:

78-55/3L Inspection of the steam inlet valve for No. 13 Auxiliary Feedwater Pump identified no apparent cause for the disengaged ste The licensee's conclusion that this is an isolated incident appears to be warrante Further review will be conducted in the event of recurrenc **

78-60/3L As stated in the Licensee Event Report, failure of the air lock door is attributed to failure to read-just the latch mechanism after door seal replace-ment. **Further inquiry by the inspector indicated that adjustment was not required since a satisfactory leak test had been accomplished following seal re-

. pl a cemen *

78-62/3L' The Licensee Event Report states that the cause of signal isolator failure is being tracked as an or (Outstanding Item #752).

The *inspector verified that the OI and the referenced DR PD-0601 were tracked to completion of the investigation, including identification of components replaced. The inspector had no questions relative to this ite /L. The cause of this occurrence was silt accumulation in a flow transmitter pressure sensing line. Periodic blowdown of the lines to prevent recurrence has been identified in the licensee's Inspection Order system *

78-64/3L This instrument channel failure was caused by an un-stable output from the trip bistable input comparato *. Analysis of the failed comparator has not been com-pleted and.is being tracked via DR PD-060 This item will be reviewed further when the failure analysis is completed (272/78-29-03).

78-66/3L This Licensee Event Report, as well as 78-56/3L, 78-58/3L, 78-60/3L, 78-68/3L and 78-75/3L, concern inoperability of the containment airlock door Most of the reported failures resulted from loss of adjustment as a consequence of con ti tiua Lus Mis-*

adjustment of the latch mechanism causes uneven seal pressure and an unsatisfactory surveillance leak tes DCR lED-0442 has been initiate*d to identify and accomplish the necessary u_pgrading of the con-tainment airlock doors to improve reliabilit Licensee actions to assure continued airlock inte-grity will be reviewed during a subsequent inspection (272/78-29-02).

.

.

.

..

78-73/lT Details of this event are discussed in NRC Inspec-tion Report 50-272/78-28, Detail paragraph 2.d. The inspector noted that :three vital instrument inverter failures* have occurred at Sal~m Unit l (LER's 78-

.

Sl(lA), 78-57(1A), 78-73(18)).

An additional failure of the 28 inverter while under load was identified at Salem~Unit An analysis is underway by the licensee to determine the generic implications of these failures. This item is unresolved pending review of licensee conclusions in.this matter (272/

78-29-01).

78-79/3L This event was caused by a clogged sensing line to a steam generator level transmitter. Slowdown of all sensing lines was accomplished and will be con-ducted periodically by inclusion into the Inspection Order syste * Except as*noted above, the inspector had no.further questions relative to Licensee Event Reports which were reviewe.

Review of Periodic and Spetial Reports Upon receipt, periodic and special reports submitted by the licensee pursuant to Technical Specifications 6.9.l and 6.9.2 are reviewed by the inspecto This review includes the following considerations:

The report includes the information.required to be reported by NRC requirements; Test results and/or supporting information are consistent with design predictions and perfo.rmance specifications;

.__

Planned corrective action is adequate for resolution of identi-.

fied problems; and, Determination whether any information in the report should be classified as an abnormal occurrence~

..!

Within the scope of the above, the following periodic.reports were reviewed by the inspector:

Monthly Operating Report - July through November 1978 One error in the October Monthly Operating Report was identified by the inspector. A corrected page has been submitted by the licensee~

The inspector had no further questions relative to the above re-view Unit 2 Preoperational Testing Quality Assurance Nonconforming conditions identified by the QA/QC organizations during surv.eillance of testing and turnover activities are identi-fied by means of Deficiency Reports (DR's).

The inspector selected a sampling of seven DR's and verified that appropriate disposition or resolution had been obtaine For those items requiring further action, the inspector verified that the completion of the actions specified was being tracked to conclusion and that any required retest as a result of the work.was identified and accomplishe The inspector had no questions relative to the items observe.

Operating Staff Training Personnel currently assigned to the performance, maintenance, and operating departments in Unit 1 will assume parallel responsibili-ties in Unit 2 when the plant becomes operationa To verify that.training and qualification of station personnel is being accomplished, the inspector attended portions of li-censed operator training, reviewed records of training for per-sonnel in the performa.nce, maintenance and operating departments, and interviewed selected personne *

The inspector identified one Technician-Nuclear whose current Level I certification had not been signed by the department hea The individual's previous (expired) certificate was properly signed.

The licensee stated that a review would be made to verify that all certificates were executed properl The inspector had no further questions relative to the abov.

Plant Tour The inspector conducted periodic tours of all a~cessible areas in the plan During these tours, the following specific items were evaluated:

Hot Wor Adequacy of fire prevention/protection measures use Fire Equipmen Operability and evidence of periodic inspection of fire suppression equipmen Housekeepin Minimal accumulations of debris and main-tenance of required clEanness levels in systems under or following testing.

Equipment preservation. Maintenance.of special pre-cautionary measures for installed equipment, as appli-cabl Component Taggin Implementation and observance of equipment ta.gging for safety or equipment protectio Fifteen tags were selected and were found to be in place as require Maintenanc Corrective maintenance in accordance with established procedure Instrumentation. Adequate protection for installed instrumentatio *Cable Pulling~ Adequate measures taken to protect cable from damage* while being pu 11 e Corrununicatio Effectiveness of public address system in all areas of the site.

  • Equipment Control Effectiveness of jurisdictional controls** in precluding unauthorized work on systems in test OJ' which have been teste Log Completeness of logs maintained and resolution of identified problem Foreign Material Exclusion. Maintenance of controls to.

assure systems which have been cleaned and flushed are not reopened to admit foreign materia Securit Implementation of security provision Parti-cular attention to maintenance of the Unit 1 protected area boundar Testing. Spot-checks of testing in pr.ogress were con-ducte The following comment applies to tours made during this in-spection period.*

A heavy, component cooling system pipe spool was found to be suspended by a wire from the yoke of valve 23CCl The situation was immediately corrected and verified by the inspecto No apparent damage to the valve yoke re-sulte The inspector had no further questions relative to observations made during plant tour~. Operational Readiness 10 CFR 50.57 states that the issuance of an operation license is, in part, contingent upon a finding that construction of the facility has been substantially completed, in conformity with the construc-tion permit and the application, as amended, the provision of the Act, and the rules and regulations of the Commission; and* that the facility will be operated in conformity with the applications as amended, the provisions of the Act, and the rules and regulations of the Commissio *

  • .:> **

.......

In order to provide a basis for this finding, the inspector is conducting a continuing review of licensee readiness to operate the facility. This review includes, but is not limited to, the following areas:

Completion of the NRC inspection program to assess construc-tion; testing and operational preparednes.

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. :* *.'

Status of facility operating procedures and personnel trainin Status of all enforcement items and unresolved matter Status of the preoperational test progra Status of construction activitie Review of licensee outstanding items, particularly those identified for completion or* resolution after core loa Review of proposed facility Technical Specification Implementation of corrective measures for Unit 2 as a result of items identified *in Unit 1 from Reportable Occurrences,_

inspectibn findings, and IE Bulletins and Circular Operational safety concerns arising from the above reviews will be promptly identified to facility management for resolution prior to the inspector reaching a finding of operational readines No specific safety conc-erns have been identified.to dat.

Unresolved Items Areas for which more information is required to determine accept-ability are considered unresolved. -Unresolved items are contained in Paragraphs 2 and 4 of this report~

1 Exit Interview At periodic intervals during the course of this inspection, meetings were held with senior facility man.agement to discuss inspection scope and findi_ngs.

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