IR 05000354/1986007

From kanterella
Revision as of 10:31, 4 December 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Radiological Controls Insp Rept 50-354/86-07 on 860121-24 & 0210 & 12-14.No Violation Noted.Major Areas Inspected: Licensee Action on Previous Findings,Bulletins,Circulars, Info Notices & Ventilation Sys Testing
ML20210D824
Person / Time
Site: Hope Creek PSEG icon.png
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)
v • d • e


Text

- . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _

>-

U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /86-07 Docket N License N CPPR-120 Priority --

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 R. L. Nimitz, Senio" Radiation Specialist 3 \ldE6

'date Approved by: ;V/. Mg _ _ 3//9 d hanbaky, nief Faci ities ' date Radiation Protection ection Inspection Summary: Inspection Summary; Inspection on January 21-24, and February 10-14, 1986. Report 50-354/86-0 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 deferra Results: No violations identified, DO K 4 hk

- -

.

.

.

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 personne .2 Nuclear Regulatory Commission
  • W. Borchardt, Senior Resident Inspector

2.0 Purpose of Inspection The purpose of the inspection was to review the following program element *

licensee action on previous inspection findings

licensee action on bulletins, circulars, and information notices (as appropriate)

a licensee deferral request of certain installed radiation monitoring 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 procedur 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)

into applicable proce:ure _-_ ___ ._

.

. 3 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 Item 50-354/85-52-05). The licensee does not plan to implement his self-monitoring program at this tim Consequently, operators were not performing independent survey .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 repor .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 responsibilitie The licensee updated administration procedures and/or Department Directives to describe the organization and per-sonnel duties and responsibilitie .8 (Closed) Follow-up Item (50-354/85-52-05)

>

Licensee to train and qualify radiation protection personnel and 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 criteri *

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). l

.

_- ..__m_____ ___m.-..__-_ ___________m___ m___ ____-___ ._.___-_-.______________ _.__--_._-

.__ _ _ _ _ _

.

.

,

3.9 (Closed) Follow-up Item (50-354/85-52-06)

'

Licensee to establish program to qual.ify Radiological Engineers .in their duties and responsibilities. Licensee established a program to prepare and qualify Radiological Engineers in their duties and responsibilitie .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.

[ 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 procedure .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 movemen The licensee established the administrative controls.

j 3.13 (Closed) Follow-up Item (50-354/85-52-10)

'

'

Licensee to establish source check procedures for audible alarming dosimeters. The licensee established procecures for checking audible alarming dosimeter .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 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 devic solved (50-354/86-07-12) This matter should be reviewed and re-prior to initial criticalit ~

=

Evaluate the adequacy of the device to properly qualify personnel exposures to beta radiatio The licensee is currently evaluating the beta response of the monitoring device.

l l

. - _ _ _ _ _ _ _

.-.

.

' 5 3.15 (0 pen) Follow-up Item (50-354/85-52-12)

Licensee to establish and implement a neutron monitoring progra 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 metho .16 (0 pen) Follow up Item (50-354/85-52-13)

Licensee to upgrade procedures for determination of skin dos The licensee stated that the required procedures will be upgrade This area will be re-examined during a future inspectio .17 (Closed) Follow-up Item (50-354/85-52-14)

Licensee to establish procedures for evaluation of off-scale self-reading dosimeter The licensee established procedures for evalua-tion of off-scale self-reading dosimeter .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 tritiu 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 tritiu .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 materia The licensee plans to use filter efficiency data developed by the vendo .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, l and operability checks of samplers prior to us i

- _ _ - _ _ - - - _ - - _ - . . . - _ - - _ - - - - _ _ - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

. .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 pla .22 (Closed) Follow-up Item (50-354/85-52-20)

Licensee to train personnel to repair respirator This matter will be reviewed in conjunction with item 50-354/86-07-0 .23 (Closed) Follow-up Item (50-354/85-52-21)

Licensee to include policy statement on facial hair into Radiation Protection Pla Licensee included policy statement on facial hair into pla .24 (Closed) Follow-up Item (50-354/85-52-24)

Licensee to upgrade job descriptions for Radiation Work Permi 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 restriction .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 hi3 h radiation and high contamination area 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 condition .26 (Closed) Follow-up Item (50-354/85-52-26)

Licensee to ensure operability of sample counters. The licensee ensured sample counters were operabl _ -

.

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 a

establishment of methodology for statistical evaluation of out-of-specification source check data

dead time correction

back-scatter correction a

self-absorption corrections

analysis of high dose rate samples a

limitations of correction factors based on actual primary 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 frisker The licensee installed, tested, and provided procedures for the frisker 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 establishe .29 (Closed) Follow up Item (50-354/85-52-30)

Licensee to establish procedures for use of source check ji Licensee established procedure for the source check ji .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 equipmen The cabinets and other facilities are adequate to support fuel loa _ _ _ _ _

_ - _ - _ - _ _ _ _ _ _ .

.

. 8 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 equipmen Following matter is open (50-354/86-07-04)

  • The whole body counter is damaged. The licensee should repair and place it in servic .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 reference 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 actio * 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 system 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

_. - - - _ - - - _ _

.

.

  • Safety Evaluations to Support Deferral of Radiation Monitoring System

-

No. PSE-SE-Z-032, Revision 1

-

No. PSE-SE-Z-033, Revision 1

-

No. PSE-SE-Z-034, Revision 1

-

No. PSE-SE-Z-035, Revision 1

- No. PSE-SE-Z-036, Revision 1

-

No. PSE-SE-Z-038, Revision 1

-

No. PSE-SE-Z-041, Revision 0

-

No. PSE-SE-Z-042, Revision 1 Within the scope of the review, the following was identified: ,-

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 loa * 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/ The alert will be set at a value less than this (@ 1.25 mR/hr). )
  • All remaining ARMS will be fully operational by about 120 days past fuel loa * The licensee has established a draft procedure for performing visual surveillance of the ARMS which are not fully operationa 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 availabl * The licensee will place into operation two portable ARMS for monitoring radiation levels inside and outside the TIP roo * Technicians will not need to enter high radiation areas to check ARM status.

i

.

L__--------- _ ____ _ _ _ - _ _ _ _ _ _ ____ ___ __

.

  • 10 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 loa *

All other monitors will be calibrated and placed in operation by 5"4 powe *

Continuous Air Monitors (CAMS) will be used to monitor airborne radioactivity concentrations in lieu of use of process monitor *

(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 loa .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*; powe *

The licensee will sample and analyze process effluent streams at a specific frequency prior to reaching 5*4 powe *

The Turbine Building Sump auto pump out will be deacti- l vated. The sump liquid will be sampled and analyzed prior I to discharg * Those process effluent monitors addressed in Technical Specifications will be checked in accordance with Specift- {

'

cation requirement .

. 11

All process liquid monitors will be calibrated and fully operational 120 days past fuel loa .4.2 Liquid Effluent Monitors Findings

The liquid effluent monitors wilk be calibrated and fully operational at fuel loa .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 identifie The licensee deferral request for ARMS is still undergoing NRR revie .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, 198 Findings 1 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

-___ _ _ _ _ _ _ _ _

i l

'

\

. 12 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 theret .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.

l

- _ _ -- -_ _ _ _ - _ _ _ _ _ _ _ _ _ _ - _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ -

.

. 13 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 effect .3.3 Information Notice 83-59, " Dose Assignment for Workers in Non-Uniform Radiation Fields," September 15, 198 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 device *

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 exposur .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:

a draft Technical Specifications

  • Final Safety Analysis Report
* Applicable ANSI and ASTM standard ..

.

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

.

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 ou The licensee will review the safety significance of this matte *

Filter mounting frame mis-alignment was identified on at least one Recirculation Uni .0 Additional Items The following matters were discussed with the license The licensee is reviewing these matters (50-354/80-07-11):

Establishment of position specific qualification criteria for Radiological Controls Supervisor Generic qualification criteria are in plac *

Establishment of operating procedures for radiological controls instrumentatio *

Upgrading of qualification criteria for determination of radiological controls technician knowledge of procedural requirement 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, 198 The inspector discussed the purpose, scope and findings of the inspectio No written material was provided to the licensee, j

L

)

Retrieved from "https://kanterella.com/w/index.php?title=IR_05000354/1986007&oldid=3313188"