IR 05000354/1986007
| ML20210D824 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/19/1986 |
| From: | Nimitz R, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20210D805 | List: |
| References | |
| 50-354-86-07, 50-354-86-7, IEB-80-10, IEC-76-03, IEC-76-3, IEC-81-07, IEC-81-7, IEIN-81-26, IEIN-82-18, IEIN-82-49, IEIN-83-59, NUDOCS 8603270066 | |
| Download: ML20210D824 (14) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-354/86-07 Docket No.
50-354 License No.
CPPR-120 Priority
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Category B
Licensee: Public Service Electric & Gas Comoany 80 Park Plaza 17C Newark, New Jersey 07101 Facility Name:
Hope Creek Generating Station Inspection At:
Hancocks Bridge, New Jersey Inspection Conducted: January 21-24, 1986 and February 10, 12-14, 1986 Inspector:
9.L dcM 3 \\ldE6 R. L. Nimitz, Senio" Radiation Specialist
'date Approved by:
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hanbaky, nief Faci ities
' date Radiation Protection ection Inspection Summary:
Inspection Summary; Inspection on January 21-24, and February 10-14, 1986.
Report 50-354/86-07.
Areas Inspected:
Routine announced radiological controls inspection of licen-see action on pervious findings, bulletins, circulars, information notices; ventilation system testing; and radiation monitoring systems deferral.
Results: No violations identified, hk
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INSPECTION DETAILS 1.0 Individuals contacted 1.1 Public Service Electric & Gas Company
- R. S. Salvesen, General Manager
- J. R. Lovell, Radiation Protection and Chemistry Manager W. Britz, Manager, Radiation Protection Services The inspector also contacted other licensee and contractor personnel.
1.2 Nuclear Regulatory Commission
- R. W. Borchardt, Senior Resident Inspector
- denotes attendance at exit meeting on February 14, 1986.
2.0 Purpose of Inspection The purpose of the inspection was to review the following program elements.
licensee action on previous inspection findings
licensee action on bulletins, circulars, and information notices
(as appropriate)
licensee deferral request of certain installed radiation monitoring a
instrumentation 3.0 Licensee Action on previous Findings 3.1 (Closed) Follow-up Item (50-354/85-44-01)
Licensee to revise radiation protection program to address'six items for improvement discussed in report 85-44.
The licensee revised the radiation protection program to address the six items for improvement (as appropriate).
3.2 (Closed) Follow up Item (50-354/85-44-02)
Licensee to establish a TIP room entry procedure.
The licensee established a TIP room entry procedure 3.3 (Closed) Follow-up Item (50-354/85-44-03)
Licensee to include time standards for conducting self-monitoring with friskers.
The licensee included a time limit (2 minutes)
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3.4 (Closed) Follow-upItem(50-354/85-44-04)
Licensee to ensure radiation protection and operation personnel are qualified to perform surveys. The licensee is currently training and qualifying radiation protection personnel to perform surveys (See
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Item 50-354/85-52-05). The licensee does not plan to implement his self-monitoring program at this time.
Consequently, operators were not performing independent surveys.
3.5 (0 pen) Follow-up Item (50-354/85-44-14)
Licensee to defer certain process and area radiation monitoring systems. This item is discussed in section 4 of this report.
3.6 Closed) Follow-up Item (50-354/85-44-15)
Licensee did not provide area radiation monitors for the traversing incore probe (TIP) room.
The licensee will install two portable area radiation monitors to monitor radiation levels inside and outside (near the TIP drives) the TIP Room.
The licensee will include these monitors into his Radiation Monitoring System (RMS).
The instal-lation and checking of this monitor will be reviewed in conjunction with follow up item (50-354/85-44-14).
3.7 (Closed) Follow-up Item (50-354/85-52-04)
Licensee to upgrade organization chart and personnel duties and responsibilities.
The licensee updated administration procedures and/or Department Directives to describe the organization and per-sonnel duties and responsibilities.
3.8 (Closed) Follow-up Item (50-354/85-52-05)
Licensee to train and qualify radiation protection personnel and
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complete task qualification sheets.
The licensee is currently revising the qualification program to address the following matters:
Licensee upgrading oral board for individuals qualified under
his old qualification program (12 technicians, 8 radiation protection assistants).
The old program did not contain clearly defined technician knowledge evaluation criteria.
Other appropriate radiation protection personnel are to be
qualified using an expanded qualification program (currently in draft).
These matters and the status of the licensee's accreditation of his program by INPO will be reviewed during a subsequent inspection (50-354/86-07-01).
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3.9 (Closed) Follow-up Item (50-354/85-52-06)
Licensee to establish program to qual.ify Radiological Engineers.in
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their duties and responsibilities. Licensee established a program to prepare and qualify Radiological Engineers in their duties and responsibilities.
3.10 (Closed) Follow-up Item (50-354/85-52-07)
Licensee to establish procedures for high' radiation area access control and entry. The licensee established procedures for access
control and entry into high radiation areas.
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3.11 (Closed) Follow-up Item (50-354/85-52-08)
Licensee to provide guidance relative to allowable radiation exposure dose rate that personnel may enter without approval.
The licensee i
established this guidance and placed it in procedures.
3.12 (Closed) Follow-up Item (50-354/85-52-09)
Licensee to establish administrative controls for fuel movement to ensure radiation protection personnel are aware of fuel movement.
The licensee established the administrative controls.
j 3.13 (Closed) Follow-up Item (50-354/85-52-10)
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Licensee to establish source check procedures for audible alarming
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dosimeters.
The licensee established procecures for checking audible alarming dosimeters.
3.14 (Closed) Follow-up Item (50-354/85-52-11)
Licensee to evaluate the high energy photon response of his personnel monitoring device.
The licensee reviewed the response characteristics of the personnel monitoring device to be used at
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Hope Creek (Panasonic). The device was found to provide an acceptable photon response in the range 30 Key to 10 MeV.
The following additional matter was identified during the review of the response characteristic of the licensee's personnel monitoring
(50-354/86-07-12) This matter should be reviewed and re-device.
solved prior to initial criticality.
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Evaluate the adequacy of the device to properly qualify
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personnel exposures to beta radiation.
The licensee is currently evaluating the beta response of the monitoring device.
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3.15 (0 pen) Follow-up Item (50-354/85-52-12)
Licensee to establish and implement a neutron monitoring program.
The licensee has not evaluated the capability of his neutron personnel monitoring device to adequately quantify neutron doses resulting from specific neutron energies which could be encountered at Hope Creek.
Pending evaluation of the licensee's dosimetry, the licensee will use a program based on time and motion method. The licensee has not yet established this method.
3.16 (0 pen) Follow up Item (50-354/85-52-13)
Licensee to upgrade procedures for determination of skin dose.
The licensee stated that the required procedures will be upgraded.
This area will be re-examined during a future inspection.
3.17 (Closed) Follow-up Item (50-354/85-52-14)
Licensee to establish procedures for evaluation of off-scale self-reading dosimeters.
The licensee established procedures for evalua-tion of off-scale self-reading dosimeters.
3.18 (Closed) Follow-up Item (50-354/85-52-15)
Licensee to include instruction for the conversion of relative humidity to airborne water concentration for determination of tritium.
The licensee revised procedures RP-SA.ZZ 002(Q) to include a conversion chart for use in determining airborne water concen-tration for determination of airborne tritium.
3.19 (Closed) Follow-up Item (50-354/85-52-17)
Licensee to reconsider need to use radioactive material to determine collection efficiency of air sampling media. The licensee deleted the procedure requirement for use of radioactive material.
The licensee plans to use filter efficiency data developed by the vendor.
3.20 (0 pen) Follow-up Item (50-354/85-52-18)
Licensee to provide procedure for issue, use, and control of lapel air samples.
Licensee added instruction for issue and control to procedure RP-TI.ZZ-003. " Control of Radiation Protection Instruments."
The following matters nave not been addressed:
limitation of use, and operability checks of samplers prior to use.
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3.21 (Closed) Follow-up Item (50-354/85-52-19)
Licensee to include policy statement for use of respirators into the Radiation Protection Plan.
The licensee included the policy state-ment into the plan.
3.22 (Closed) Follow-up Item (50-354/85-52-20)
Licensee to train personnel to repair respirators.
This matter will be reviewed in conjunction with item 50-354/86-07-01.
3.23 (Closed) Follow-up Item (50-354/85-52-21)
Licensee to include policy statement on facial hair into Radiation Protection Plan.
Licensee included policy statement on facial hair into plan.
3.24 (Closed) Follow-up Item (50-354/85-52-24)
Licensee to upgrade job descriptions for Radiation Work Permit.
Licensee upgraded Radiation Work Permit procedure to include special precautions to ensure workers and radiation protection personnel clearly understand the specific scope of work and work restrictions.
3.25 (0 pen) Follow-up Item (50-354/85-52-25)
Licensee to upgrade Radiation Work Permit (RWP) procedure to provide special guidance as to when special precautions and instructions should be considered. To address the matter, the licensee prohibited use of Extended RWPs in hi h radiation and high contamination areas.
However, the licensee does not have a mechanism in place to readily identify situations requiring changes to the RWP to upgrade radio-logical controls on the RWP based on changing conditions.
3.26 (Closed) Follow-up Item (50-354/85-52-26)
Licensee to ensure operability of sample counters. The licensee ensured sample counters were operabl _
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The following matters will be reviewed prior to fuel load (50-354/86-07-02).
establishment of operating procedures for counting equipment
establishment of control charts for appropriate laboratory
sample counting instrumentation establishment of methodology for statistical evaluation of a
out-of-specification source check data dead time correction
back-scatter correction
self-absorption corrections a
analysis of high dose rate samples
limitations of correction factors based on actual primary a
coolant activity filter loading corrections
3.27 (Closed) Follow-up Item (50-354/85-52-28)
l Licensee to install, test, and provide operating procedures for the I
protal friskers.
The licensee installed, tested, and provided procedures for the friskers.
The following matter remains open (50-354/86-07-03):
determination of system sensitivity
3.28 (Closed) Follow-up Item (50-354/85-52-29)
Licensee to install and test respirator test station.
The licensee installed and tested the station.
Operating procedures have been established.
3.29 (Closed) Follow up Item (50-354/85-52-30)
Licensee to establish procedures for use of source check jig.
Licensee established procedure for the source check jig.
3.30 (Closed) Follow-up Item (50-354/85-52-31)
Licensee to put in place sufficient cabinets and other storage facilities to store protection clothing and equipment.
Licensee put in place sufficiert cabinets and other storage facilities to store protection clothing and equipment.
The cabinets and other facilities are adequate to support fuel load.
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3.31 (Closed) Follow-up Item (50-354/85-52-32)
Licensee to relocate and set-up whole body counting and respirator fit equipment.
The licensee relocated and set up equipment.
Following matter is open (50-354/86-07-04)
The whole body counter is damaged. The licensee should repair
and place it in service.
3.32 (0 pen) Follow-up Item (50-354/85-52-40)
Licensee to upgrade Radiological Occurrence Report (ROR) System.
The licensee upgraded procedure RP-AP.ZZ-111Q, " Radiological Occurrence Report System," to correct incorrect references.
Inspector review of this procedure and procedure RP-AP.ZZ-103, " Trending Program,"
identified the following matters needing licensee attention:
the licensee's program for trending RORs did not provide clear
guidance for evaluating trends in RORs and initiation of appropriate corrective action.
the ROR System does not provide for timely corrective action
to prevent recurrence 4.0 Radiation Monitoring System Deferral 4.1 General The licensee has requested the deferral of certain process and area monitoring systems.
The inspector reviewed the licensee's deferral request with respect to criteria contained in the following:
Letter, R. L. Mittl (PSEG) to W. Butler (NRC) dated
September 10, 1985 Letter W. Butler, (NRC) to C. McNiel (PSEG), dated
November 21, 1985 Letter C. McNiel (PSEG) to E. Anderson (NRC),
dated December 26, 1985
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Safety Evaluations to Support Deferral of Radiation Monitoring System
No. PSE-SE-Z-032, Revision 1
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No. PSE-SE-Z-033, Revision 1
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No. PSE-SE-Z-034, Revision 1
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No. PSE-SE-Z-035, Revision 1
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No. PSE-SE-Z-036, Revision 1
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No. PSE-SE-Z-038, Revision 1
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No. PSE-SE-Z-041, Revision 0
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No. PSE-SE-Z-042, Revision 1
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Within the scope of the review, the following was identified:
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4.2 Area Radiation Monitoring (ARMS) System Findings The Control Room, New Fuel Storage, and Spent Fuel Sterage ARMS
will be calibrated and fully operational by fuel load.
The remaining ARMS will be calibrated and fully operational
(locally) by fuel load The high alarm set point on the ARMS will be set at 2.5 mR/h.
- The alert will be set at a value less than this (@ 1.25 mR/hr).
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All remaining ARMS will be fully operational by about 120 days
past fuel load.
The licensee has established a draft procedure for performing
visual surveillance of the ARMS which are not fully operational.
The ARMS will be locally checked once per shift prior to initial criticality and twice per shift thereafter until they become fully operational. The readout indication in the Control Room may not be available.
The licensee will place into operation two portable ARMS for
monitoring radiation levels inside and outside the TIP room.
Technicians will not need to enter high radiation areas to
check ARM status.
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- 4.3 Ventilation Monitors 4.3.1 Process Ventilation Monitor Findings The Control Room, Refuel Floor Exhaust and Reactor Building
Exhaust Monitor will be calibrated and fully operational by fuel load.
All other monitors will be calibrated and placed in
operation by 5"4 power.
Continuous Air Monitors (CAMS) will be used to monitor
airborne radioactivity concentrations in lieu of use of process monitors.
(ARMS will be checked once per shift prior to initial
criticality and twice per shift thereafter until the process ventilation monitors become fully operational (120 days after fuel load).
4.3.2 Effluent Ventilation Monitors Findings All effluent ventilation monitors (North and South Plant
Vent and the Facility Recirculation Vent System (FRVS)
vent) will be calibrated and fully operational at fuel load.
4.4 Liquid Monitors l
4.4.1 Process Liquid Monitors Findings The Process Liquid Effluent Monitor will be calibrated and
operative (locally) prior to 5*; power.
The licensee will sample and analyze process effluent
streams at a specific frequency prior to reaching 5*4 power.
The Turbine Building Sump auto pump out will be deacti-
vated.
The sump liquid will be sampled and analyzed prior to discharge.
Those process effluent monitors addressed in Technical
Specifications will be checked in accordance with Specift-
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All process liquid monitors will be calibrated and fully
operational 120 days past fuel load.
4.4.2 Liquid Effluent Monitors Findings The liquid effluent monitors wilk be calibrated and fully
operational at fuel load.
4.5 Conclusion Based on the above review, the licensee is establishing and imple-menting the compensatory measures committed to in the documentation to the NRC. No deficiencies were identified.
The licensee deferral request for ARMS is still undergoing NRR review.
5.0 Bulletins, Circulars and Information Notices The inspector reviewed the licensee's actions, (as appropriate) on the following bulletin, circulars and information notices:
5.1 Bulletins IE Bulletin 80-10. " Contamination of Nonradioactive system and
Resulting Potential for Unmonitored, Uncontrolled Release to the Environment," May 6, 1980.
Findings
The following matters are being reviewed and resolved by the licensee: (This bulletin remains open.)
sampling and analysis of plant air systams
establishment of value for declaring a system contaminated
(i.e. Lower Limit of Detectability (LLD))
selection of sampling and analysis programs to meet LLD
chemistry technician actions upon identification of a
contaminated system operations shift actions upon notification of a contaninated
system
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5.2 Circular?.
5.2.1 IE Circular 76-03, " Radiation Exposures In Reactor Cavities,"
September 13, 1976 Findings The licensee is reviewing and will resolve the following matter (50-354/86-07-13).
Training of personnel in locations of transient and unusually
high radiation areas, and access requirements thereto.
5.2.2 IE Circular 81-07, " Control of Radioactively Contaminated Material," May 8, 1981
Findings The following matters are being reviewed and resolved by the licensee (50-354/86-07-05):
selection of appropriate criteria for release of poten-
tially contaminated material definition / description of instrumentation to ensure
conformance with criteria for release No apparent measurement techniques / methodology is estab-
lished for aggregate waste measurements 5.3 Information Notices 5.3.1 Information Notice 82-18, " Assessment of Intakes of Radioactive Material by Workers," June 11, 1982 Findings The following matters are being reviewed and resolved by the licensee (50-354/86-07-06):
The licensee does not have in place procedures for determination
of radioactive material intake by individuals based on whole body counting results.
5.3.2 IE Information Notice No. 81-26, " Compilation of Health Physics Related Information Items," August 2,1981.
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Findings The following matters are being reviewed and resolved by the licensee (50-354/86-07-07):
The licensee does not have full controls in place for calibra-
tion and use of portable radiation survey instrumentation to minimize geometry and angular dependance effects.
5.3.3 Information Notice 83-59, " Dose Assignment for Workers in Non-Uniform Radiation Fields," September 15, 1983.
Findings The following matters are being reviewed and resolved by the licensee (50-354/86-07-08):
Procedures provide insufficient and inconsistent guidance
for use of additional personnel monitoring devices.
Procedures do not ensure proper placement of personnel
dosimetry based on maximum dose to be received to a parti-cular portion of the body.
The procedures also failed to consider non-uniformity of radiation exposure.
5.3.4 Information Notice 82-49, " Correction for Sample Conditions for Air and Gas Monitoring," December 16, 1982 Findings The following rnatters are being reviewed and resolved by the licensee (50-354/86-07-09):
No administrative controls or guidance was in place to
ensure airborne radioactivity sampling equipment used in the field was set-up and operated consistent with calibra-tion limitations (e.g. used with proper length of hose).
6.0 Safety Related Ventilation System Testing The inspector reviewed selected elements of the licensee's testing of safety related ventilation systems.
The review was with respect to criteria contained in the following:
draft Technical Specifications a
Final Safety Analysis Report
Applicable ANSI and ASTM standards.
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The licensee's performance was based on the following:
inspector review of data
inspector discussions w;th cognizant personnel
independent observation of on going testing including visual
inspections of the interior of filter trains Findings
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The following matters are being reviewed and resolved by the licensee (50-354/86-07-10):
Roughing filters in the Recirculation Filter Trains are being
blown out.
The licensee will review the safety significance of this matter.
Filter mounting frame mis-alignment was identified on at least one
Recirculation Unit.
7.0 Additional Items The following matters were discussed with the licensee.
The licensee is reviewing these matters (50-354/80-07-11):
Establishment of position specific qualification criteria for
Radiological Controls Supervisors.
Generic qualification criteria are in place.
Establishment of operating procedures for radiological controls
instrumentation.
Upgrading of qualification criteria for determination of radiological
controls technician knowledge of procedural requirements.
The results of the licensee's review of these matters will be examined during a subsequent inspection, 8.0 Exit Meeting
The inspector met with licensee representatives (denoted in section 1)
on February 14, 1986.
The inspector discussed the purpose, scope and findings of the inspection.
No written material was provided to the licensee, j
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