IR 05000458/1998006

From kanterella
Jump to navigation Jump to search
Insp Rept 50-458/98-06 on 980427-0501.No Violations Noted. Major Areas Inspected:Implementation of Liquid & Gaseous Radioactive Effluent Waste Mgt Program
ML20247M600
Person / Time
Site: River Bend Entergy icon.png
Issue date: 05/19/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20247M586 List:
References
50-458-98-06, 50-458-98-6, NUDOCS 9805260312
Download: ML20247M600 (20)


Text

1

.

l

.

ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket No.: 50-458 License No.: NPF-47 Report No.: 50-458/98-06 Licensee: Entergy Operations, In Facility: River Bend Station Location: 5485 U.S. Highway 61 St. Francisville, Louisiana l I

Dates: April 27 through May 1,1998 Inspector: J. Blair Nicholas, Ph.D., Senior Radiation Specialist l

Plant Support Branch Approved By: Blaine Murray, Chief, Plant Support Branch Division of Reactor Safety ATTACHMENTS:

Attachment 1: SupplementalInformation Attachment 2: Effluent Release Data l \

! l l

l l

l

9805260312 980519 PDR ADOCK 05000458 G PDR

-

_ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ _

.

.

-2-EXECUTIVE SUMMARY River Bend Station NRC Inspection Report 50-458/98-06 This announced, routine inspection reviewed the implementation of the liquid and gaseous radioactive effluent waste management program. Training and qualifications, quality assurance oversight, facilities and equipment, and annual reports were also reviewe Plant Suooort

-

Overall, a good liquid and gaseous radioactive effluent waste management program was implemented which included proper implementing procedures, a qualified staff, and appropriate quality assurance oversigh Challenging performance goals were initiated and met in 1996 and 1997 for the reduction of radioactive effluent waste releases. A significant reduction in the amount of liquid waste effluent volume and activity discharged was noted in 1996,1997, and the first quarter of 1998. These reductions resulted from changes and improved methods used to process the liquid waste water, which provided for its reuse. Since 1995, the gaseous

.

effluent activity released has shown a slight increase (Section R1.1).

  • A good in-place filter and charcoal adsorber testing program was implemented for the standby gas treatment system, control room ventilation system, and fuel building ventilation system (Section R1.2).

+ The radiochemistry counting room was equipped with properly maintained and calibrated analytical instrumentation (Section R2.1).

Liquid and gaseous effluent radiation monitors were properly maintained, tested, and calibrated (Section R2.2).

- Proper procedures were maintained which contained appropriate detail. Good annual radioactive effluents release reports for 1995,1996, and 1997 were submitted in a timely manner and contained the required information. Revisions to the Offsite Dose Calculation Manual were appropriately implemented and documented (Section R3.1).

-

Chemistry personnel had a very good understanding of the liquid and gaseous radioactive effluent waste management procedures and Technical Requirements Manual. Health physics personnel were very knowledgeable of the dose calculation procedures and Offsite Dose Calculation Manual methodologies (Section R4).

_ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _

.

-3-

- Training and qualification programs for chemistry technicians and health physics specialist were properly implemented. The chemistry and radiation protection departments had well trained and qualified staffs for conducting radioactive waste effluent processing, release operations, and performing effluent dose calculations (Section R5).

- An appropriate chemistry technical staff was maintained which had experienced little change since the last NRC inspection of the radiological effluento management program in March 1996 (Section R6).

- Oversight of the radioactive effluent waste management program was adequat Contractor laboratories used to perform radioactive effluent waste management program Technical Requirements Manual surveillance test analyses were properly evaluated (Section R7).

l l

l l

.

-

!

,

-4-l Report Details l

l IV. Plant Suonort R1 Radiological Protection and Chemistry Controls R1.1 Radiological Waste Effluent Manaaement Proarams Insoection Scooe (84750)

Implementation of the radioactive effluent waste management program was reviewe This review included: radioactive effluent waste processing, radioactive effluent waste sampling and analyses, offsite dose results, and surveillance tests. The following documentation was reviewed:

. Selected batch radioactive liquid waste effluent release permits for the period January 1997 through March 1998

. Selected gaseous waste effluent sample analyses for samples from the plant's main stack vent, fuel building vent, and radwaste building vent continuous releases for the period January 1997 through March 1998 The following activities were observed:

-

The collection of effluent samples from the main plant vent radiation monitor for analyses of particulate and iodine Observations and Findinas On April 28,1998, the inspector observed the collection of the air particulate filter sample and iodine charcoal cartridge sample from the main plant vent. The inspector noted that the nuclear chemistry technician followed the appropriate sampling procedure while performing the sample collections. The inspector observed that the nuclear chemistry technician used proper sample handling techniques when collecting and analyzing the semples. All aspects of the sample collections and analyses were properly performe he inspector verified that the processing, sampling, analyses, and monitoring of the batch liquid radioactive waste effluents and continuous releases of the gaseous radioactive waste effluents were conducted properly. Quantities of radionuclides released in the liquid and gaseous radioactive effluent wastes were within the limits specified in the Technical Requirements Manual. Offsite doses were calculated according to Offsite Dose Calculation Manual methodologies and were within regulatory j limits. Required analyses of monthly and quarterly composite samples of liquid and l gaseous radioactwe waste effluents were properly performed as specified in the i Technical Requirements Manua l l

-

.

-5-

Effluent release data reported in the annual effluent release reports for 1995,1996, and {

1997, which are summarized in Attachment 2 to this report, showed a decrease in the number of batch liquid radioactive effluent releases. Challenging performance goals for ]'

the volume and activity of liquid radioactive waste discharged were initiated and met in 1996 and 1997, and the reduction trend continued in 1998. The liquid effluent data showed a significant reduction in the volume and activity discharged in 1996 and 199 Between 1995 and 1997, the volume of liquid wasto discharged was reduced by approximately 75 percent, and the activity discharged was reduced by approximately 80 percent. These reductions were due to improved methods used to process the waste water and remove total organic carbon contaminates. This improved purification allowed the processed waste water to meet the chemistry criteria to be recovered and retumed to the condensate storage tank for reuse, therefore, reducing the amount of liquid radioactive waste effluents discharged. Even though significant progress has been made in the reduction of liquid radioactive waste discharged from the plant, the plant's liquid effluent data when compared with the industry's effluent data for boiling water reactors showed the plant's liquid effluent performance for the 1994-1996 3-year rolling average was in the third quartile. However, a continuation of present performance should place the plant's liquid waste effluent performance in the range that is better than the boiling water reactor's national average for the 1995-1997 3-year average tren The licensee's gaseous effluent data, when compared with the industry's gaseous effluent data for boiling water reactors, showed that between 1994 and 1996 the amount of gaseous curies released was in the third quartile for airbome gas, in the fourth quartile (worst) for airborne iodine / particulate (due to fuel leaks), and in the second quartile for airborne tritium. The 1997 gaseous effluent data showed a slight increase in the amount of activity release The licensee informed the inspector that they were aware of their status in the industry relative to their effluent discharges and stated that improvement in the reduction of effluent radioactivity released from the plant had a high priorit l The licensee reported no unplanned releases of radioactive liquid or gaseous waste during 1995-199 Conclusions The liquid and gaseous radioactive effluent waste management program was effectively

, implemented. Challenging performance goals were initiated and met in 1996 and 1997

'

for the reduction of liquid radioactive effluent waste releases. A significant reduction in the amount of liquid waste effluent volume and activity discharged was noted in 1996, 1997, and the first quarter of 1998. These reductions resulted from changes and improved methods to process the waste water, which provided for its reuse. Since 1995, the gaseous effluent activity released has shown a slight increase.

t

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

l l .

-6-

!

l R1.2 - Enoineered-Safetv-Feature Filtration and Control Room Habitability Systems

! Insoection Scone (84750)

! Selected surveillance and test results for the engineered-safety-feature air cleaning ventilation systems' testing program were reviewed to determine compliance with the requirements in the Technical Requirements Manua Observations and Findinas The inspector and two system engineers performed an external visual inspection of the filter housings of the standby gas treatment system, fuel building ventilation system, and control room fresh air ventilation system. These systems contained high efficiency particulate air filters and activated charcoal adsorbers. The visual inspection of the ventilation filtration systems indicated no problems. ' All filter housing doors were tightly closed, and all door gaskets were in place and not leaking. All filter housings and ducts were well maintained. The areas surrounding the filtration units were clean, free of debris, and adequate lighting was provided for visual inspection of housings and component The inspector verified that the surveillance tests for toe three safety-related ventilation l filtration systems provided for the required periodic functional testing of the filtration systems' components, evaluation of the high efficiency particulate air filters and activated charcoal adsorbers, and the in-place filter testing. The inspector reviewed the last performed surveillance tests' results for each of the three safety-related air cleaning ventilation systems and verified that the previous surveillance tests were performed at the required 18-month frequency. The licensee performed tha in-place filter testing. An offsite contractor laboratory performed the activated charcoal iodine removal efficiency tests. The surveillance test results met Technical Requirements Manual requirement Conclusions A good in-place filter and charcoal adsorber testing program was implemented for the standby gas treatment system, control room ventilation system, and fuel building ventilation syste I R2 Status of Radiological Protection and Chemistry Facilities and Equipment R Radiochemistry Countina Room Insoection Scooe (84750)

The radiochemistry counting facility and associated analytical instrumentation were inspected to verify if adequate calibration and quality control programs were in plac l

_ - _ _ - _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ - _ _ _

._ _ - _ _ _ _ _ _ - _ _ - _ _ _ - _ _ _ _ _ - - _ _ _ - _ . ___

.

-7-l Observations and Findinos The radiochemistry counting room maintained the appropriate analytical instrumentation to perform the required radiochemistry analytical measurements of the radioactive effluent waste samples. Quality control indicators were tracked and trended for the gamma spectroscopy, liquid scintillation, and gross alpha counting systems. Data showed that the instruments were operable, weil maintained, and calibrated. The nuclear chemistry technicians were trained and knowledgeable on the use of the instrumentatio Conclusion The radiochemistry counting room was equipped with properly maintained and calibrated analyticalinstrumentation.

l R2.2 Liguid and Gaseous Effluent Radiation Monitors Insoection Scooe (84750)

Selected liquid and gaseous effluent radiation monitors were inspected for operation, calibration, and reliability. The liquid and gaseous radioactive waste effluent radiation monitor source check, channel check, channel functional test, and channel calibration records were reviewed to determine compliance with the Technical Requirements Manual requirement Observations and Findinos Source checks, channel checks, channel functional tests, and calibrations were properly .

performed on the liquid and gaseous effluent radiation monitors. Surveillance test records indicated that the liquid and gaseous radioactive waste effluent monitoring instrumentation was properly maintained, tested, and calibrated in compliance with the surveillance requirements specified in the Technical Requirements Manua Conclusion Liquid and gaseous effluent radiation monitors were properly maintained, tested, and calibrate R3 Radiological Protection and Chemistry Procedures and Documentation R Radioactive Waste Effluent Procedures. Technical Requirements Manual. Offsite Dose Calculation Manual. and Annual Radioactive Effluent Release Reoorts Insoection Scooe (84750)

Procedures for the sampling, analysis, and release of radioactive liquid and gaseous waste effluents were reviewed. Revisions to the Offsite Dose Calculation Manual were

-- _ - _ _ _ _ _ _ _ _ _ -

_ . _ _ _ _- __ _ _ __ _________------ - ____ ._ _ ___________ _ ___ _____ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

r___________.---___

'

8-reviewed for any changes to the radioactive effluent waste programs and the radwaste system design and operation. The annual radioactive effluent release reports for 1995, 1996, and 1997 were reviewe b. Observations and Findinos l

Chemistry procedures described the responsibilities for collection and analyses of liquid l and gaseous radioactive effluent waste samples. Procedures for batch and continuous j release of liquid and gaseous radioactive waste effluents provid9d proper instruction for l

'

sampling, analyses, release permit generation, release limits, monitoring, and approval Radiation protection procedures described the responsibility for calculation of effluent doses and provided proper guidance in the use of the dose calculation methodologies described in the Offsite Dose Calculation Manual. The chemistry and radiation protection procedures were written with sufficient detail to effectively conduct the required radioactive waste effluent program activitie The annual radioactive effluent release reports were written in the format described in NRC Regulatory Guide 1.21, Revision 1, June 1974, and contained the required information. Summaries of the quantities of radioactive liquid and gaseous effluents released to the environment and their associated doses to members of the public for 1995-1997, were properly documented in the annual reports. A summary of the radioactive liquid and gaseous effluent releases and associated doses is presented in Attachment 2 to this repor Revisions 6 and 7 to the Offsite Dose Calculation Manual were issued since the last NRC inspection in March 1996. The changes were documented in the appropriate annual radioactive effluent release reports. The inspector determined that the changes did not reduce the effectiveness of the radioactive effluent waste management progra c. Conclusions Implementing procedures for the liquid and gaseous radioactive effluent waste management program provided proper guidance. Good annual radioactive effluent release reports for 1995,1996, and 1997 were submitted in a timely manner and contained the required information. Revisions to the Offsite Dose Calculation Manual were properly documente R4 Staff Knowledge and Performance a. Insoection Scoce (84750)

Chemistry and radiation protection personnel were observed and interviewed to evaluate their knowledge and performance of radioactive effluent waste activities.

l

_ _ _ _ - - _ - _

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

.

. b. Observations and Findinas The inspector observed nuclear chemistry technicians perform radioactive effluent waste activities and determined that they were familiar with the requirements of the radioactive effluent waste management program. Chemistry personnelincluding supervisors and technicians maintained a high level of performance and were knowledgeab!e of the liquid and gaseous radioactive effluent waste management procedures, Technical Requirements Manual, and Offsite Dose Calculation Manual requirements. Batch radioactive liquid waste effluent releases and continuous radioactive gaseous waste effluent releases were. properly performed during 1996-199 The health physics / chemistry specialist assigned to perform the effluent dose l- calculations was trained and qualified. Conclusions Chemistry and radiation protection personnel had a very good understanding of the liquid l and gaseous radioactive effluent waste management procedures, Technical L Requirements Manual. Health physics personnel were very knowledgeable of the dose j calculation procedures and Offsite Dose Calculation Manual methodologie R5 Staff Training and Qualification a. Insoection Scooe (84750)

Training and qualification programs for the nuclear chemistry technicians involved with conducting the radioactive waste effluent management programs and the health physics / chemistry specialist involved with the calculation of the effluent doses were reviewed and verified.

I b. Observations and Findinas

[

l Using computerized training records of qualification tasks completed, the inspector

! verified that 13 of 14 nuclear chemistry technicians were fully qualified to independently .'

l perform routine radioactive effluent waste management program activities. One new

'

nuclear chemistry technician was in the process of completing the appropriate task I qualifications. The inspector determined that proper training and qualification programs

'

were being implemented for the nuclear chemistry technicians and health physics / chemistry specialist.

I c. Conclusions l

Training and qualification programs for the chemistry technicians and health physics / chemistry specialist were properly implemented. The chemistry and radiation protection departments had well trained and qualified staffs for conducting radioactive waste effluent processing, release operations, and performing effluent dose calculation ,

l l

l

- _ _ - _ _ _ - _ _ _ _ _ _ _ - _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ _ _ . __ _ .

l-10-R6 Radiological Protection and Chemistry Organization and Administration Insoection Scooe (84750)

The organization, staffing, and assignment of the radioactive waste effluent management l program responsibilities were reviewed. Chemistry and radiation protection I departmental procedures were reviewed for the assignment of responsibilities for the management and implementation of the radioactive waste effluent management progra Observations and Findinas The chemistry department was responsible for implementing the radioactive waste j effluent management program with assistance from the radwaste operations department i for performing liquid waste release discharges. The radiation protection department was responsible for performing the liquid and gaseous effluent dose calculations and tracking release data and dose The staffing levels of the chemistry and radiation protection departments were sufficient to perform the duties required by the radioactive effluent waste management progra The chemistry staff implementing the program had remained essentially the same since the last NRC inspection in March 1996. There were only one new chemistry technician and a new chemistry superintendent. The inspector noted that the qualifications of the J j chemistry superintendent were appropriate and met Technical Specification l requirements. The health physics / chemistry specialist responsible for the effluent dose l calculations was new since the previous NRC inspection of this area. The organization ,

l and staffing of the chemistry and radiation protection departments were appropriate for I implementing the liquid and gaseous effluent management program.

l

' Conclusions An appropriate chemistry technical staff was maintained which had experienced little change since the last NRC inspection of the radiological effluents management program in March 199 R7 Quality Assurance in Radiological Protection and Chemistry Activities Insoection Scoce (84750)

The quality assurance audit program regarding radioactive effluent waste management program activities was reviewed. The review included the audits and self-assessments performed between September 1996 and March 199 The quality assurance audit and evaluation program regarding contractors performing surveillance activities involving the radioactive effluent waste management programs and safety-related air cleaning ventilation systems were reviewe _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - _ - - _ _ _ _ _ _ - _ - _ - _ - - _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ -

.

-11- Observations and Findinas A good quality assurance audit of chemistry activities was performed. The audit of chemistry activities was performed on a 24-month frequency and provided adequate oversight of radioactive effluent waste management program activities. Technical specialists were used on the audit teams from other utilities. Audit team members had previous experience in the areas reviewed and were qualified auditor Audits of contractor laboratories used to perform radiochemistry analyses on radioactive effluent waste composite samples and laboratory charcoal adsorber analyses on the station's safety-related air cleaning ventilation systems were evaluated for inclusion on the qualified suppliers list. These audits were performed by Nuclear Procurement issues Committee audit teams led by various utilities with interest in the services provided by the contractor laboratories. The inspector determined that the audits performed on the contractor laboratories were satisfactory to evaluate the contractors' abilities to perform their respective Technical Requirements . Manual required analyses and surveillance activitie Conclusions Oversight of the radioactive effluent waste management program was adequat Contractor laboratories used to perform radioactive effluent waste management program Technical Requirements Manual surveillance test analyses were properly evaluate R8 Miscellaneous Radiological Protection and Chemistry Issues R (Closed) Violation 9703-01: Failure to Determine Drv Active Waste Stream Scalina Factors The inspector verified that the corrective actions described in the licensee's response letter, dated October 9,1997, were implemented. No similar problems were identifie R8.2 (Closed) Violation 9703-01: Failure to Validate Tvoe A Waste Stream Scalina Factors Biennially The inspector verified that the corrective actions described in the licensee's response letter, dated October 9,1997, were implemented. No similar problems were identifie R8.3 (Closed) Violation 9703-03: Failure to Correctiv Calculate the Quantity of Radioactivity of a Shioment l The inspector verified that the corrective actions described in the licensee's response letter, dated October 9,1997, were implemented. No similar problems were identifie ;

I l

l j

. _ ._

.- _

_-_ .__- ___________ _ -__ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ _ _

!

.

!

! .

.

-12-V. Manaaement Meetinas X1 Exit Meeting Summary l The inspector presented the results of the inspection to members of licensee management at the conclusion of the inspection on May 1,1998. The licensee acknowledged the findings presented. No proprietary information was identifie !

l

!

i

!

!

l

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

_ _ _ _ _ _ - _ _ - _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _

.

.

ATTACHMENT 1 SUPPLEMENTAL INFORMATION PARTIAL LIST OF PERSONS CONTACTED Licensee  ;

J. Anderson, Technical Specialist, Quality Assurance L. Ballard, Supervisor-Quality, Quality Assurance R. Bellamy, Acting Site Vice President R. Biggs, Coordinator, Nuclear Safety and Regulatory Affairs K. Bomeman, System Engineer, Heating Ventilation and Air Conditioning R. Buell, Acting Director, Site Support D. Burnett, Senior Health Physics / Chemistry Specialist, Chemistry P. Chapman, Superintendent, Chemistry 1 D. Deal, Acting Superintendent, Radiation Controls l C. Fantacci, Radiation Protection Technical Specialist, Radiological Programs ,

D. Heath, Supervisor - Radwaste, Radiological Programs l T. Hildebrandt, Acting Plant Manager i H. Holmes Health Physics / Chemistry Specialist, Radiation Programs B. Houston, Manager, Licensing l V. Huffstatler, Senior Health Physics / Chemistry Specialist, Radiation Programs M. Jurey, Supervisor, Instruments and Controls C. Lewis, Supervisor - Chemistry /Radwaste, Chemistry D. Lorfing, Supervisor, Licensing A. Maryman, Supervisor - Chemistry / Radiation Control, Chemistry R. McDougald, System Engineer, Heating Ventilation and Air Conditioning W. O'Mally, Manager, Operations A. Roshto, Superintendent, instruments and Controls W. Spell, Supervisor - Radiation Protection Operations, Radiological Controls P. Wright, Radwaste Specialist, Chemistry C. Young, Supervisor - Chemistry / Radiation Control, Chemistry NBC G. Replogle, Senior Resident inspector N. Garrett, Resident inspector LIST OF INSPECTION PROCEDURES USED IP 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring I

- _ _ - - - _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ __ _

-

!

.

-2-LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Closed 50-458/9703-01 VIO Failure to Determine Dry Active Waste Stream Scaling Factors 50-458/9703-02 VIO Failure to Validate Type A Waste Stream Scaling Factors Biennially 50-458/9703-03 VIO Failure to Correctly Calculate the Quantity of Radioactivity of a Shipment LIST OF DOCUMENTS REVIEW'ID ORGANIZATION CHARTS Chemistry Department - April 1998 Radiological Programs - April 1998 TRAINING DOCUMENTATION Chemistry department training records Chemistry / Health Physics Specialist train:ng record TPP-7-017 " Training and Qualification of Nuclear Chemistry Technicians," Revision 6, May 27,1997 QUALITY ASSURANCE DOCUMENTS 1998 Quality Assurance Internal Audit Schedule QAD-18 " Audits," Revision 13, April 14,1998 QAl- " Audit Process," Revision 16 October 10,1997 Quality Assurance Audit Chemistry Department Assessment / Audit (97-03-1-CHEM) conducted March 17-21,1997 Offsite Dose Calculation Manual Program Audit (96-06-I-ODCM) conducted June 10-19,1996

\

!

_- __-___-______-_____-__-___-_ -

- - _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ - _ - _ - _ _ _ _ _ _ _ - _ _ _ _ _ _

!

l 3-

I l Vendor Audits
NUPlc Joint Quality Assurance Audit of Yankee Atomic Environmental Laboratory, conducted l June 19-20,1995 NUPIC Joint Quality Assurance Audit of NCS Corporation, conducted November 18-21,1996 l PROCEDURES

Chemistrv Procedgas l

l COP-0046 " Sampling Gaseous Effluents via the Wide Range Gas Monitors," Revision 9, !

i December 2,1996 l l

l CSP-0100 " Chemistry - Required Surveillance and Actions," Revision 17B, I l January 21, YO8 CSP-0110 " Radioactive Liquid Effluent Batch Discharge," Revision 13, February 7,1996 l i

i Radiation Protection Procedures l l

RPP-0097 " Manual Method of Determining Cumulative Dose Contributions from Liquid l

'

Effiuents," Revision 5, October 16,1996

!

l RPP 0102 " Dose Calculations from Gaseous Effluents," Revision 5, October 16,1996 i RHP-0032 " Dose Rate Calculation from Gaseous Effluents," Revision 5, October 16,1996 l

'

Surveillance Tests

'

STP-511-4550 "RMS-Liquid Radwaste Effluent Line Radiation Monitor Channel Functional Test RMS-RE107," Revi:: ion 7A STP-511-4280 . "RMS-Liquid Radwaste Effluent Line Radiation Monitor Channel Calibration RMS-RE107," Revision 8 STP-311-4581 "RMS-Radiation Mo,1itor Cooling Tower Blowdown Line Channel Functional Test RMS-RE108," Revision 6 STP-511-4281 *RMS-Radiation Monitor Ceding Tower Blowdown Line Channel Calibration RMS-RE108," Revision 7 STP-000-0201 " Monthly Onerating Log," Revision 17 i STP-000-0001 " Daily Operating Log," Revision 25

'

i

!

. l-4-STP-511-4514 "RMS-Main Plant Exhaust Duct Noble Gas Activity Channel Functional Test RMS-RE-125," Revision 7 STP-511-4214 "RMS-Main Plant Exhaust Duct Noble Gas Act!vity Channel Calibration i Test RMS-RE-125," Revision 6 l

STP-511-4537 ' " Main Plant Exhaust Duct Mcnitoring System Flow Rate Monitor Channel l Functional Test RMS-FEX-125, RMS-FEY-125," Revision OB j

!

!

STP-511-4237 . " Main Plant Exhaust Duct Monitoring System Flow Rate Monitor Channel l Calibration RMS-FEX-125, RMS-FEY-125," Revision 4 -j i

STP-511-4538 * Main Plant Exhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Functional Test RMS-FTX-125, RMS-FTY-125," Revision 0 STP-511-4238 " Main Plant Exhaust Duct Monitoring System Sampler Flow Rate Monitor l Channel Calibration RMS-FTX-125, RMS-FTY-125," Revision 6

!

STP-511-4515 "RMS-Main Plant Exhaust Duct Noble Gas Activity Channel Functional ,

! Test RMS-RE-126," Revision 6 l

l \

l STP-511-4215 "RMS-Main Plant Exhaust Duct Noble Gas Activity Channel Calibration j Test RMS-RE-126," Revision 7

.

STP-511-4531 " Main Plant Exhaust Duct Monitoring System Flow Rate Monitor Channel Functional Test RMS-FE-126," Revision 0 STP-511-4231 " Main Plant Exhaust Duct Monitoring System Flow Rate Monitor Channel i

!

Calibration RMS-FE-126," Revision 6 i

STP-511-4532 " Main Plant Exhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Functional Test RMS-FEX-126," Revision 0 STP-5114232 " Main Plant Exhaust Duct Monitoring System Sampler Flow Rate Monitor  ;

Channel Calibration RMS-FEX-126," Revision 7 l

!

STP-511-4505 "RMS/SCIS-Fuel Building Ventilation Exhaust Radiation-High Channel Functional Test RMS-RESA," Revision 10A

,

,

STP-511-4205 "RMS/SCIS-Fuel Building Ventilation Exhaust Radiation-High Channel Calibration Test RMS-RE5A," Revision 7C STP-511-4533 " Fuel Building Exhaust Duct Monitoring System Flow Rate Monitor Channel Functional Test RMS-FESA," Revision 0 STP-511-4233 " Fuel Buildhg Exhaust Duct Monitoring System Flow Rate Monitor Channel Calibration RMS-FESA," Revision SA

,

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

_ _ _ _ . _ _

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - -

.

.

-5-STP-511-4535 " Fuel Building Exhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Functional Test RMS-FTX5A, RMS-FTYSA," Revision 1 STP-511-4235 " Fuel Building Exhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Calibration RMS-FTX5A, FTYSA," Revision 7 STP-511-4506 "RMS/SCIS-Fue! Building Ventilation Exhaust Radiation-High Channel Functional Test RMS-RE58," Revision 7A STP-511-4206 "RMS/SCIS-Fuel Building Ventilation Exhaust Radiation-High Channel Calibration Test RMS-RE5B," Revision 9

]

I

'

STP-511-4534 " Fuel Building Exhaust Duct Monitoring System Flow Rate Monitor Channel Functional Test RMS-FE58," Revision 0 STP-511-4234 " Fuel Building Exhaust Duct Monitoring System Flow Rate Monitor Channel Calibration RMS-FE5B," Revision 7 STP-5114536 " Fuel Building Exhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Functional Test RMS-FEX58," Revision OA l

STP-511-4236 " Fuel Building Exhaust Duct Monitoring System Sampler Flow Rate l Monitor Channel Calibration RMS-FEX5B," Revision 9 STP-511-4516 "RMS-Radwaste Building Ventilation Exhaust Duct Noble Gas Activity Monitor Channel Functional Test RMS-RE6A," Revision 7 STP-511-4216 "RMS-Radwaste Building Ventilation Exhaust Duct Noble Gas Activity Monitor Channel Calibration Test RMS-RE6A," Revision 6 STP-511-4539 "RMS-Radwaste Building Ventilation Exhaust Duct Monitoring System Flow Rate Monitor Channel Functional Test RMS-FE6A," Revision OA STP-511-4239 "RMS-Radwaste Building Ventilation Exhaust Duct Monitoring System Flow Rate Monitor Channel Calibration RMS-FE6A," Revision 5 STP-511-4541 "RMS-Radwaste Building Ventilation Exhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Functional Test RMS-FTX6A, RMS-FTY6A," Revision 0 l STP-511-4241 *RMS-Radwaste Building Ventilation Exhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Calibration RMS-FTX6A, RMS-FTY6A." Revision 6 i

STP-511-4517 "RMS-Radwaste Building Ventilation Exhaust Duct Noble Gas Activity Monitor Channel Functional Test RMS-RE68," Revision 6 l

l

_ _ _ _ _ _ _ _ _ . -_-_______ _ __ - ___ a

_ _ _ _ _ _ _ _ _ __ _ . _ - _ _ . _ _ _ _ _ _ _ _ _ _ _ .

,

'

l l

l

l-6- I

'

STP-511-4217 "RMS-Radwaste Building Ventilation Exhaust Duct Noble Gas Activity Monitor Channel Calibration Test RMS-RE6B," Revision 5

"

STP-511-4540 . RMS-Radwaste Building Ventilation Exhaust Duct Monitoring System Flow Rate Monitor Channel Functional Test RMS-FE6B," Revision 0 STP-511-4240 "RMS-Radwaste Building Ventilation Exhaust Duct Monitoring System Flow Rate Monitor Channel Calibration RMS-FE68," Revision 8A l l

STP-511-4542 "RMS-Radwaste Building VentilationExhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Functional Test RMS-FEX68,"

Revision 0 STP-511-4242 "RMS-Radwaste Building Ventilation Exhaust Duct Monitoring System Sampler Flow Rate Monitor Channel Calibration RMS-FEX6B," Revision 5 MISCELLANEOUS DOCUMENTS Selected liquid radioactive waste batch release permits Engineered-safety feature air cleaning systems surveillance test records Annual Radioactive Effluent Release Reports - 1995,1996, and 1997 i RSP-0008 "Offsite Dose Calculation Manual," Revision 7, March 30,1998 l

l l

l

._________________-_-_________-_a

_

_

6 ? 4 2- 3 7 5 3 + 7 -

9 3 5 8 7 E 9 4 E E 9 3 3 97 1 0 3 9 8 5 0 0 7

4 1 2 1 4 6 1 0 0

i 2 8 6

_

J

'

S

_

S E 6 S ="

E 2 7 + A a 7 2- 3

-

S 6 5 5 6 8 E E 8 9 9 6 4 9 E E 9 A 9 3 3 0 0 5 L 9 2 4 2 0 8 E 1

0 5 9 E 1 0 8 6 2 L 0 2 5 3 E

7 R J -

'

R T v"

.

T N N E E U .t

' -

L U F 2 L F F E

_ T F N E E E D N M I R ,#

H U O C Q I / B 1 3-A L 5 7 2 +: R 5'

3 -

T 7 4 4 1 E E L 9 8 1 t IA 9 0 4 T L 9 2 0 0 4 9 6 4 6 A 1 5 1 1 9 L 1 6 5 8 2

_

A 2 2 L - 1 2 3 F A O F

- N O -

O c

_

_

.

I N

O

-

_

_ T A

.

I

_

T -l M A

_

_ M M

_

_ U M cc )

_

_

S )

s U s s

_

e s y

.

_

ir e S ier a

_

u s u d

_ a

_

C ( ~

G )

s C ( 8 r

>

-

- s le e t s

t c b it c s

_

s u o l( u e e ,

) v

-

s d N d d o s i

- a o r e >

r ie L

d s -

e P e ) a P r f )

_

-

le R

h n

o it a

ia n

r ir s

e u R e

le n

o C it a 1 (

u H

la h

s ier u

c v

)

s t

n C v 31 it C )

s t

a E ( e (

it ie m it c w ie B c r

& a u e

-

s a r f A u h A in e h u o & C d p lo & d t lp C r ( e) lA V la) A (

e n vs e n lo u s m b o m u loie s s t o l ce it ri s

s u mis sr o s is a r u o it u is it s u a is t

o aC r i ir r r N F T i D(C G W F T P( G T f

-

e s

o 1 0 00 0

'D 83 57 1 1 7 31 7 7 02 23 8 9 00 00 0

. 9 i

A S

E S

A

-

~

N6 +

E

5

7

E S 3 3 0 L , E 4 0 E S 0 R

T A

E L

M7 N

E U

e s

E R

N o 90 00 0 L 82 61 6 D D

F N

I 44 03 2 U F 6 07 1 1 5 E 9 00 00 0

.

Q $ 6

. 9 I

+ 2 9 D L 5 NE 1 6 I

n N 3 4 U I 5 0 Q

I T b 9 07 0

)

t n

.

L D

N E

T h

N o

c N A

N $

$

(

. .- O 2 S ;

,

C $

!

T U E b N O .-

N7

- I 2 E E R M S e s U + 0 5 C 3 H A o 00

00

0

4 6 G D 8 C

A T

T M

O

9

63

01

22

7 N D

A ME

$

9

1

0 A R F

-

E M

N d

S U E E L !.

O S

O D

V h L

A U

.

.

F O

N h

h )s t n it r

e O r e e L N

h I

t /

N T it l

n e C o k

i A U e C r

u D

U

)

m e

D E

h (m lu ru ie C o

R

!

i

',-

-

r m

R h5 o

V C ic M

r X )

d ( k

$

A ) a s s $

M -

m r 3t,ey I q e (

m ) 3 lau a 1 d h

$};

r s e -

m ) t s o)

eic8 I ( n Des dint >

t r s c e

- t a a s

.

_

nyr ed t

I lu f

f Es(

iAD lope r o

,di v luoG f

B(

r 1 nL -

s aai A 31 af,l

-

f Een uGm( a d lo a ih o

elema emH

-

u g inu t

r sb ae it h iWO L

q GN aoGB dit r loTw i