IR 05000311/1986033

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Insp Rept 50-311/86-33 on 861104-07.No Violations Noted. Major Areas Inspected:Radiological Safety Program,Including Status of Previously Identified Items,Control of Outage Work & Status of Radiation Protection Procedures Rev
ML18092B377
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/12/1986
From: Dragoun T, Shanbaky M
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18092B375 List:
References
50-311-86-33, NUDOCS 8612230190
Download: ML18092B377 (6)


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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /86-33 Docket N license N DPR-75 Category ~

Licensee:

Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Facility Name:

Salem Generating Station Unit 2 Inspection At:

Hancocks Bridge, New Jersey Inspection Conducted:

November 4-7, 1986 Inspector:

Approved by: !?fl:J-/Yb dat~

/z/;z/yt date Inspection Summary:

Inspection on November 4-7, 1986 (Report No. 50-311/86-33)

Areas Inspected:

Routine, unannounced inspection of the radiological safety program including:

status of previously identified items; control of outage work; status of radiation protection procedures revision; and personnel dosime-tr Results:

No violations were identifie DETAILS 1.0 Persons Contacted During the course of this routine safety inspection the following personnel were contacted or interviewed: Licensee Personnel J. Zupko, General Manager - Salem L. Miller, Assistant Superintendent J. Trejo, Radiation Protection Manager D. Mohler, Radiation Protection Engineer R. Patwell, Licensing E. Browder, Station QA NRC Personnel K. Gibson, Resident Inspector T. Kenny, Senior Resident Inspector All above personnel attended the exit interview on November 7, 1986 2.0 Purpose The purpose of this routine inspection was to review the licensee's radia-tion protection program with respect to the following elements:

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0 Status of previously identified items,

Control of Out~ge work Replacement procedures Personnel dosimetry 3.0 Status of Previously Identified Items 3.1 (Closed) Followup Item (272/79-15-01) The minimum detectable level of I-131 in RHR liquid is higher than 10 CFR 20 Appendix B limit Since I-131 levels in RHR are normal, this matter is no longer a con-cer.2 (Closed) Followup Item (272/81-18-01) Review transportation trainin Training is periodically provide The latest session was held on April 198.3 (Closed) Followup Item (311 & 272/84-09-02) Review potential unmoni-tored radioactivity release paths during outages per IEB 80-1 Pro-cedure AP-13 "Temporary Jumpers, Pumps, and Lifted Leads" specifies the precautions for use of temporary pumps to transfer contaminated fluid.4 (Closed) Followup Item (311 & 272/84-09-03) Implement revised radia-tion protection procedure Status of this item is discussed in sec-tion 5.0 of this repor.5 (Closed) Followup Item (311 & 272/84-21-01) Issue ALARA Manua The manual was issued by Radiation Protection Services on September 9, 198.6 (Closed) Followup Item (311 & 272/84-21-02) ALARA engineer to coord-inate man-rem estimate Procedure AP-7 11ALARA Program 11 requires that the ALARA supervisor include man-rem goals in the pre-job check-list.7 (Closed) Follow-up Item (311 & 272/84-21-03) Establish review of HP procedures for regulatory complianc In accordance with Technical Specification Amendment 33 and procedure AP-32, all revised RP proce-

. dures are checked by a qualified reviewer to *ensure procedural com-pliance with the applicable regulation *

3.8 (Closed) Followup Item (311 & 272/84-21-04) Expand procedure for res-ponse to CAM alar Revision 3 to procedure RP8.031 11Use of the Eberline AMS II Beta Continuous Area Monitoring System 11 provides com-plete emergency instruction.9 (Closed) Followup Item (272/84-35-01) Review dose assessment of 3 workers cleaning the steam generato The license~s calculations and methodology were reviewed and found acceptabl.10 (Closed) Violation (272/84-35-02) Ensure that procedures require up-per arm dosimetry in certain radiation field Procedure RP3.021 11Multiple Special TLD Badging 11 was revised to include situations re-quiring that upper arm exposures be monitore The corrective action described in licensee letter dated December 19, 1984 is complete and satisfactor.11 (Closed) Followup Item (311/84-44-01) Review revised Lapse of Radio-logical Controls (LRC) procedur Procedures RP 1.025 11 Procedure for Processing of LRC 11 was revised and RPl.030 11Generating a Radiological Occurrence Report 11 was issued to encourage workers to report radio-logical deficiencie.12 (Closed) Followup Item (272/84-45-11) Finalize procedures for inplant radioiodine samplin Procedure EP-lV-123 11 Emergency Inplant Air Sampling*r and EP-lV-118 11 High Activity Sample Analysis 11 were issued in November 198 Both procedures were reviewed and determined to be adequat.13 (Closed) Followup Item (272/84-45-12) Review new respirator training progra Respirator training is now a separate 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> session that includes practical factors and a final exa Lesson plan TP-211 Rev.I provides adequate technical informatio *

3.14 (Closed) Followup Item (311/85-12-01) Provide new job descriptions for RP departmen Position descriptions are now available for new staff position.15 (Closed) Followup Item (272/85-17-01 and 311/85-19-01) Verify correct-ive action regarding improper sampling of waste gas decay tank Chemistry technician training lesson plan #150 has been revised to include a detailed review of LER 85-0 This would provide for pro-per sampling of the waste gas decay tank.16 (Closed) Followup Item (272/85-21-01) and 311/85-23-01) Limit work assigned to HP technicians in training. A memo issued by the Radia-tion Protection Engineer on September 23, 1985 limits trainee work assignment Revision 11 to procedure RP4.001 "Radiation Protection Survey Schedules" requires a review of surveys performed by trainees by an ANSI qualified technicia.17 (Closed) Followup Item (272 and 311/86-13-01) Incorporate ALARA in-formation in lesson plans for contractor HP technician Lesson plan

  1. 404 Rev.01 issued August 22, 1986 incorporates a discussion of the station ALARA progra.18 (Closed) Followup Item (272 and 311/86-13-02) Provide formal guidance for screening qualification of contractor HP technician Procedure RP 2.001 "Radiation Protection Qualification Program" was revised to include this guidanc.19 (Open) Unresolved Item (272 and 311/86-13-03) Establish a firm sched-ule and revise RP procedure The procedures to be revised have been identified and a completion schedule has been issue This major procedure change is further discussed in section.0 Control of Outage Work The licenseels safety program for the control of outage work was reviewed with respect to the criteria contained in:

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Technical Specification 6.11 Radiation Protection Program Technical Specification 6.8 Procedures and Programs 10 CFR 20 Standards for Protection Against Radiation Reg Guide 1.33 Rev.2 (February 1978) Appendix A Station procedures RPl.013, RPl.017, RPl.030 and RPIP230 The licensees performance relative to these criteria was determined from:

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0 Review of active RWPs and supporting radiation surveys Tour of the work areas Discussions with RP supervisors and technician*

Review of the Radiological Occurrence Reports

Within the scope of this review no violations were observe The inspec-tor noted the following changes were implemented by the licensee in an effort to enhance the program:

Procedure RPIP230 11 Radiation Work Permits 11 is the first in a series of new procedures issued under the RP procedures overhaul progra This proce-dure is not SORC committee approved per the recent amendment 33 to the Technical Specification The procedure was reviewed by RP department personnel onl The inspector reviewed RP1P230 and found that it provided clear, explicit instruction However, the computer generated RWP form was cluttered with extraneous data such that the radiological conditions and protective measures may not be immediately evident to the worker.* The licensee is aware of this problem and plans to simplify the for This matter will be reviewed in a future inspectio (86-33-01)

The licensee assigned six senior technicians specific outage work packages to be followed from preplanning stages through job completio This coord-ination and planning improved job performance and resulted in significant dose savings in a few instance The refueling exposure goal for Unit-2 was 75 man-rem of which 55 man-rem was use The Salem site goal was 720 man-rem for 1986 of which about 560 man-rem was use For the year to date there were 219 Radiological Occurrence Report The majority of these reports concerned personnel contamination, lost dosime-try and violations of RWP requirement The inspector noted that the lic-ensee1 s ability to identify radiological deficiencies, identify trends, and take appropriate corrective action has improve.0 RP Procedures Revisions The procedures revision project was discussed fully in inspection report 86-1 During this inspection the licensee stated that draft revised RP procedures would be completed by September 1987 and fully implemented by December 198 On November 10, 1986 the licensee published a detailed schedule that identified the new procedures, assigned responsibility to the RP staff, and provided completion date This will ensure completion of all procedure revisions and training of personnel prior to the 1987 Unit 1 outag The inspector noted that the current timetable for this project is acceptabl.0 Personnel Dosimetry The licensee recently lengthened the processing interval of TLD badges from monthly to quarterl This change was implemented to allow badging all personnel on the Hope Creek/Salem site The impact of this change was assessed through discussions with the Dosimetry Supervisor and a review of licensee test data and manufacturers (Panasonic) data regarding TLD fadin.....

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Within the scope of this review, no violation was observe The TLD fad-ing over a 3 month interval is small and predictabl Various cross checks such as TLD-SRP comparisons, use of control badges, and TLD glow curve analysis are used to identify anomalie These controls ensure the accuracy of personnel exposure report However, the difficulties in assessing personnel exposures when dosimetry is lost and other potential technical problems will--be assessed in a future inspection after the imple-mentation of this new syste.0 Exit Interview

The inspector met with the personnel denoted in section 1 at the conclus-ion of this inspection on November 7, 198 The scope and findings of the inspection were discussed at that time.