IR 05000361/1998008

Insp Repts 50-361/98-08 & 50-362/98-08 on 980727-31.No Violations Noted.Major Areas Inspected:Plant Support

ML20237D079
Person / Time
Site:	San Onofre
Issue date:	08/19/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20237D076	List: IR 05000361/1998008 ML20237D074
References
50-361-98-08, 50-361-98-8, 50-362-98-08, 50-362-98-8, NUDOCS 9808250032
Download: ML20237D079 (19)

Text

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

.

ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket Nos.: 50-361 50-362

]

License Nos.: NPF-10 NPF 15 Report No.: 50-361/98-08 50-362/98-08 Licensee: Southern California Edison C Facility: San Onofre Nuclear Generating Station, Units 2 and 3 Location: 5000 S. Pacific Coast Hw San Clemente, California Dates: July 27-31,1998

~

Inspector: J. Blair Nicholas, Ph.D., Senior Radiation Specialist Plant Support Branch Approved By: Blaine Murray, Chief, Plant Support Branch Division of Reactor Safety Attachment: Supplemental information

' 9808250032 980819 PDR ADOCK 05000361 .

G PDR

,

e

)

l

'

I 2-EXECUTIVE SUMMARY

. San Onofre Nuclear Generating Station, Units 2 and 3 NRC Inspection Report 50-361/98-08; 50-362/98-08 This announced, routine inspection reviewed the implementation of the liquid and gaseous radioactive waste effluent management program. Training and qualifications, quality assurance oversight, facilities and equipment, and annual reports were also reviewe Plant Support

Overall, an effective liquid and gaseous radioactive waste effluent management program was implemented which included proper implementing procedures, a qualified staff, and good analytical instrumentatio *

Generally, the liquid and gaseous radioactive waste effluent management program was properly implemented. A small reduction in the amount of liquid waste effluent volume discharged was noted from 1996 to1997. The station's curie amount of liquid effluent discharged showed a slight decreasing trend since 1993. Since 1995, the gaseous effluent activity released also showed a decreasing trend (Section R1.1).

The in-place filter and activated charcoal testing programs were properly implemented for the control room emergency air cleanup system and fuel handling building post-accident cleanup filter system (Section R1.2).

• The radiochemistry counting room's analyticalinstruments were properly maintained and calibrated (Section R2.1).

Ten liquid and eight gaseous effluent radiation monitors were operable and properly maintained, tested, and calibrated. Eight new effluent radiation monitors were installed but not calibrated and operational at the time of the inspection (Section R2.2).

• Implementing procedures for the liquid and gaseous radioactive waste effluent management program provided proper guidance. The annual radioactive effluents release reports for 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 waste effluent management program procedures and Offsite Dose Calculation Manual requirements (Section R4).

• Training and qualification programs for chemistry technicians and radwaste operators were properly implemented. The chemistry and operations departments had well trained and qualified staffs for conducting sampling and analyses, radioactive waste i

effluent processing and release operations, and performing effluent dose calculations (Section RS).

.

.

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

!

,

-3-

An appropriate chemistry technical staff and radwaste operations staff were maintained (Section R6).

Oversight of the radioactive waste effluent management program was good. In 1998, l the chemistry department led a comprehensive performance based self-assessment of I the radioactive waste effluent management program. Contractor laboratories used to i perform radioactive waste effluent management program Technical Specification and )

Offsite Dose Calculation Manual surveillance test analyses were properly evaluated (Section R7).

l

A non-cited violation was issued for a licensee identified violation of Technical Specification 5.5.2.3 involving the failure to establish an operating procedure to

)

{

implement the surveillance requirement in Offsite Dose Calculation Manual 4.1.1.2, I which required the verification and recording that all circulating water pumps required to provide dilution were operating and providing dilution when required. The root cause of l this non-cited violation (50-361/9808-01) was the failure to include the surveillance test in the initial development of the operating procedures. The circumstances surrounding this violation satisfied the criteria for discretion as described in Section Vll.B.1 of the Enforcement Policy (Section R8.1).

)

l

1

,

l

!

i ._ _

--_____ _____ - ____ -

.

.

Report Details IV. Plant Suppo_rt R1 Radiological Protection and Chemistry Controls R1.1 Radiological Waste Effluent Manaaement Proarams Insoection Scope (84750)

Implementation of the liquid and gaseous radioactive waste effluent management prc~ ns, as described in the Offsite Dose Calculation Manual, was reviewed. This

!

revi v included the performance of the following required surveillance activities:

rad oactive effluent waste processing, radioactive waste effluent sampling and analyses, ar 2lyticallower limits of detection, and offsite dose results. The following radioactive e aste effluent program documentation was reviewed:

Ten batch radioactive liquid waste effluent release permits for the period January 1997 through July 1998 from the radwaste secondary tanks, miscellaneous waste condensate monitor tanks, and full flow condensate polisher demineralized holdup tanks.

' .

Eleven gaseous waste effluent release permits for the period January 1997 through July 1998 from the waste gas decay tanks and containmen *

Selected gaseous waste effluent sample analyses of continuous release samples from the plant vent stack and Units 2 and 3 condenser air ejectors for the period January 1997 through July 199 The following activities were observed:

The collection of gaseous effluent samples from the Unit 2 condenser air ejector radiation monitor and the performance of radiochemistry analyses for airborne particulate and iodine, noble gases, and tritium.

l

• The collection of gaseous effluent samples from the plant vent stack radiation l monitor and the performance of radiochemistry analyses for airborne particulate and iodine, noble gas, and tritiu j l 1 i * The collection of a waste liquid sample from the Unit 2 full flow condensate !

l polisher demineralized holdup tank, performance of chemistry and radiochemistry '

l analyses, preparation of the clean sump release authorization, and performance l of the valve lineup and discharge of the holdup tank.

I

!

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

.

.

5- Observations and Findinos The chemistry technicians carried and referred to the appropriate sampling procedures while performing the sample collections. Proper sample handling techniques were used when collecting and analyzing the samples. All aspects of the sample collections and analyses were properly performed. The radioactive liquid and gaseous waste effluent releases were performed in accordance with approved procedures and the Offsite Dose Calculation Manual requirement Quantities of radionuclides released in the liquid and gaseous radioactive waste effluents were within the limits specified in the Offsite Dose Calculation Manual. Offsite doses were calculated according to Offsite Dose Calculation Manual methodologies and were within regulatory limits. Required analyses of monthly and quarterly composite samples of liquid and gaseous radioactive waste effluents were properly performed as specified in the Offsite Dose Calculation Manua I in 1997, the radioactive liquid effluent data showed a decrease in the volume j discharged. The curie amount of radioactive liquid effluent mixed fission and activation products released between 1993 and 1996 showed a declining trend. However, in 1997 an activity increase was noted in the liquid waste effluent as a result of the Unit 2 Cycle 7 steam generator tube plug leaks. The curie amount of liquid tritium released between  !

1993 and 1995 remained relatively constant with an increase in 1996 due to an increase j

'

in tritium from six liquid waste effluent batch releases made during the fourth quarter of 1996. However, the curie amount of liquid tritium released in 1997 showed a significant decrease with a resulting improvement in the station's liquid tritium release performance, The station's year-to-date curie amount of radioactive liquid waste effluent discharged met the 1998-anticipated goa Since 1994, the gaseous effluent fission and activation data showed a decreasing trend in the amount of activity discharge Conclusions l

The liquid and gaseous radioactive waste effluent management program was properly '

implemented. A small reduction in the amount of liquid waste effluent volume discharged was noted from 1996 to1997. The station's overall curie amount of liquid effluent discharged showed a slight decreasing trend since 1993. Since 1995, the gaseous effluent activity released has also shown a decreasing tren R1.2 Enaineered-Safetv-Feature Filtration and Control Room Habitability Systems Inspection Scope (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 Specifications.

(

l l

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

.

6- Observations and Findinas The inspector and system engineer performed an external visualinspection of the filter housings of the co itrol room emergency air cleanup filter system (Trains A and B) and the fuel handling building post-accident cleanup filter system (Trains A and B) for Units 2 and 3. These systems contained high efficiency particulate air filters and activated charcoal adsorbers. The 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. The filter housings were well maintained. The areas surrounding the filtration units were clean,iree of debris, and adequate lighting was provided for inspection of housings and component The inspector verified that the surveillance tests for the two safety-related ventilation 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, and the in-place filter testing. The inspector reviewed the results of the last performed surveillance tests for each of the two safety-related air cleaning ventilation filter systems and verified that previous surveillance tests were performed at the required 18-month frequency. The licensee performed the in-place filter testing, and an offsite contractor laboratory performed the activated charcoal iodine removal efficiency tests. Generally, the surveillance test results met ventilation filter testing program acceptance criteria. However, since the previous NRC inspection of the safety-related ventilation filtration systems, the licensee had implemented new testing requirements for the activated charcoal. The inspector noted that the test results from the initial test of all the activated charcoal using the new testing criteria did not meet the acceptance requirements. As a result of the test failures, the licensee had replaced all the activated charcoal in the filtration units with new charcoal which was tested and met the new testing criteri Conclusions Good in-place filter and charcoal testing programs were implemented for the control room emergency air cleanup system and fuel handling building post-accident cleanup filter syste R2 Status of Radiological Protection and Chemistry Facilities and Equipment R Radiochemistry Countino Room Insoection Scope (84750)

The radiochemistry counting room's analytical instrumentation was inspected to verify that adequate calibration and quality control programs were implemente Observations and Findinas The radiochemistry counting room maintained the appropriate analytical instrumentation p to perform the required radiochemistry analytical measurements of the radioactive waste

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

!

!

l-7-(

'

effluent samples. Quality controlindicators were tracked and trended for the gamma spectroscopy, liquid scintillation, and gross alpha counting systems. Data showed that the instruments were operable, well maintained, and calibrated.

i

' Conclusion

!

The radiochemistry counting room's analytical instruments were properly maintained i and calibrate R2.2 Liauid and Gaseous Effluent Radiation Monitors

! Insoection Scoce (84750)

l The liquid and gaseous effluent radiation monitors were inspected for operation, testing, and calibration. The source check, channel check, channel functional test, and channel calibration records for the liquid and gaseous radioactive waste effluent radiation monitors were reviewed to determine compliance with the Offsite Dose Calculation Manual requirements, Observations and Findinas Source checks, channel checks, channel functional tests, and calibrations were properly performed at the required frequency on the liquid and gaseous effluent radiation monitors. Surveillance test records documented 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 Offsite Dose Calculation Manua The licensee was in the process of replacing eight older effluent radiation monitors in Units 2 and 3 with new effluent radiation monitors. The new monitors were installed, but the testing and caEbration had not been complete Conclusion Liquid and gaseous effluent radiation monitors were operable and properly maintained, tested, and calibrated. Eight new effluent radiation monitors were installed but not calibrated and operational at the time of the inspectio R3 Radiological Protection and Chemistry Procedures and Documentation R3.1 - Radioactive Waste Effluent Procedures. Offsite Dose Calculation Manual. and Annual Radioactive Effluent Release Reports

! Inspection Scope (84750)

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

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

I 8- '

reviewed for any changes to the radioactive waste effluent program. The annual I radioactive effluent release reports for 1996 and 1997 were reviewe b. Observations and Findinas

Chemistry procedures described the responsibilities for collection and analyses of liquid l and gaseous radioactive effluent waste samples. Procedures for batch and continuous release of liquid and gaseous radioactive waste effluents provided proper instruction for sampling, analyses, release permit generation, release limits, monitoring, and approvals. Chemistry procedures also provided proper guidance in the use of the quality controlled computer software to perform dose calculations in accordance with the dose calculation me:hodologies described in the Offsite Dose Calculation Manual. The chamistry 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 informatio Revisions 29,30, and 31 to the Offsite Dose Calculation Manual were issued since the last NRC inspection in January 1997. 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 waste effluent management progra c. Conclusions Implementing procedures for the liquid and gaseous radioactive waste effluent management program provided proper guidance. The annual radioactive effluent release reports for 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 personnel were observed and interviewed to evaluate their knowledge and performance of radioactive waste effluent activitie b. Observations and Findinas The inspector observed chemistry technicians performing radioactive waste effluent activities and determined that they were familiar with the requirements of the radioactive waste effluent management program. Chemistry personnelincluding supervisors and technicians maintained a high level of performance and were knowledgeable of the liquid and gaseous radioactive waste effluent management procedures and Offsite Dose Calculation Manual requirements. Batch and continuous radioactive liquid and gaseous

!

I i

___-- __ _ - _ - __ __ _ _ __ __ ___ -_- _______________ __ __ _ ____ _ __ _ _-_ - _ _ _ _ _ _ _ _ - _ _ _ _ _ _ -

.

.

-9-waste efflant releases were properly performed during the period January 1997 l through July 199 c. Conclusions

!

! Chemistry personnel had a very good understanding of the liquid and gaseous l radioactive waste effluent management program procedures and Offsite Dose l Calculation Manual requirement R5 Staff Training and Qualification a. Insoection Scooe (84750)

Training and qualification programs for the chemistry technicians and radwaste operators involved with conducting the radioactive waste effluent management program were reviewed. Training program descriptions, selected lesson plans, and qualification i guides for the chemistry technicians and radwaste operators were reviewe b. Observations and Findinas l {

l Using training and qualification records, the inspector verified that 20 of 21 chemistry

'

,

technicians were qualified to independently perform routine radioactive waste effluent

'

management program activities which included the calculation of effluent doses. One recently hired chemistry technician was in the process of completing the required task qualifications to independently perform radioactive waste effluent management program l activities. The inspector also verified that each of the six operating shifts were staffed with at least 10 trained and qualified radwaste operators, who routinely performed waste effluent release activities and operated the radioactive waste processing equipmen c. Conclusions Training and qualification programs for chemistry technicians and radwaste operators were properly implemented. The chemistry and operations departments had well i trained and qualified staffs for conducting sampling and analyses, radioactive waste l effluent processing and release operations, and performing effluent dose calculation !

R6 Radiological Protection and Chemistry Organization and Administration

. a. Insoection Scope (84750)  ;

'

l The organization, staffing, and assignment of the radioactive waste effluent i management program responsibilities were reviewed. Chemistry departmental  !

procedures were reviewed for the assignment of responsibilities for the management and implementation of the radioactive waste effluent management program.

I

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

.

-10- Observations and Findinas The chemistry department was responsible for implementing the radioactive waste effluent management program with support from the radwaste operators when performing liquid and gaseous waste effluent batch releases. The staffing levels of the chemistry and radwaste operations departments were sufficient to perform the duties required by the radioactive waste effluent management program. The chemistry staff implementing the radioactive waste effluent management program had remained essentially the same with the addition of seven formerly qualified chemistry technicians returning to the chemistry department as a result of a reorganization since the last NRC inspection in January 1997. The effluent chemistry supervisor's position was permanently filled with the former acting effluent chemistry supervisor, the chemistry manager was replaced as a result of staff reassignments, and one new chemistry technician was hired since the previous NRC inspectio The inspector noted that the qualifications of the effluent chemistry supervisor and chemistry manager met Technical Specification requirements. The radwaste operator crews were adequately staffed, and radwaste personnel had not changed significantly during the past 18 months. The organization and staffing of the chemistry department and the operations shift crews were appropriate for implementing the liquid and gaseous

. radioactive waste effluent management program, Conclusions An appropriate chemistry technical staff and radwaste operations staff were maintained since the last NRC inspection of the radioactive waste effluent management program in January 199 R7 Quality Assurance in Radiological Protection and Chemistry Activities Inspection Scoce (84750)

The quality assurance program of the radioactive waste effluent management program and Offsite Dose Calculation Manual were reviewed. The following items were reviewed:

• Qualifications of personnel who performed the quality assurance audits and activity observations;

• Quality assurance activity observation reports performed during the time period January 1997 through July 1998;

• Technical Specification Improvement Project program self-assessment dated l March 6,1998; and

• Self-assessment of the Units 2 and 3 Offsite Dose Calculation Manual and surveillance requirements performed during the time period April through June 199 !

(

L

_ _ _ _____________ - _- _ -- _ _ _

-11-The quality assurance audit and evaluation program of the contractor laboratories performing surveillance tests and sample analyses required by the radioactive effluent waste management program and the safety-related air cleaning ventilation systems'

filter testing program were reviewe Observations and Findinas A quality assurance audit of the radioactive effluent waste management program had not been performed since the previous NRC inspection of this area. The next audit of the Offsite Dose Calculation Manual and the radioactive effluent management program is scheduled for September 199 During the time period April through June 1998, a multi-disciplined team led by the chemistry department performed a comprehensive self assessment of the radioactive waste effluent management program and Offsite Dose Calculation Manual and its implementing procedures. The self-assessment was performed by technical personnel who had work experience in the areas assessed. Quality assurance activity observation reports were performed by qualified auditors. The quality assurance program and self-assessments provided good oversight of radioactive waste effluent management program activitie Audits of contractor laboratories used to perform radiochemistry analyses of radioactive waste effluent composite samples and charcoal analyses on the station's safety-related air cleaning ventilation filter systems were used to evaluate the contractors' performance and to maintain the two laboratories' acceptance as qualified suppliers on the licensee's routine 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 of the two contractor laboratories met the requirements to properly evaluate the contractors'

abilities to perform their respective Technical Specification and Offsite Dose Calculation Manual required analyses and surveillance activitie Conclusions Oversight of the radioactive waste effluent management program was goo Contractor laboratories used to perform radioactive waste effluent management program Technical Specification and Offsite Dose Calculation Manual surveillance test analyses were properly evaluate R8 Miscellaneous Radiological Protection and Chemistry issues R8.1 (Closed) LER 50-361/1998-06: Missed Technical Specification Surveillance Due to Initial Procedural Error On April 21,1998, during a review of the Units 2 and 3 Offsite Dose Calculation Manual, Revision 31, the licensee identified a procedural inadequacy to satisfy the Units 2 and 3 Offsite Dose Calculation Manual dilution pump operation surveillance requirement for l

i

.

-12-liquid waste effluent releases. The original surveillance requirement in the Units 2 and 3 Technical Specifications was to verify every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> that all pumps required to provide dilution were operating and providing dilution, when dilution was required. In 1990, the surveillance requirement was transferred from the Units 2 and 3 Technical Specification 4.3.3.8.2 to the Units 2 and 3 Offsite Dose Calculation Manual 4.1.1.2. Units 2 and 3 Offsite Dose Calculation Manual, Revision 31, changed the 4.1.1.2 surveillance requirement frequency from 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to read, "At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or after a change in plant mode or pump lineup has been completed, all pumps required to be providing dilution to meet site radioactive effluent concentration limits of Specification 1.1.1 shall be determined to be operating and providing dilution to the discharge structure." This was the first time this surveillance requirement had been changed and reviewed since the surveillance requirement was transferred from the Units 2 and 3 Technical Specifications to the Units 2 and 3 Offsite Dose Calculation Manual in 199 Historically, between 1982 and 1998, existing operating procedure revisions did not provide instruction for the performance of the surveillance requirement. Specifically, between 1982 and 1990, Units 2 and 3 Technical Specification 4.3.3.8.2 surveillance requirement and between 1990 and 1998 Units 2 and 3 Offsite Dose Calculation Manual 4.1.1.2 surveillance requirement were not performed during liquid effluent releases which were greater than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in duration. This event was identified by the licensee as a violation involving the failure to establish an operating procedure to implement the Offsite Dose Calculation Manual as required by Technical Specification 5.5.2.3. The licensee identified that the root cause of this event was personnel error during the initial development of the operating procedures in 198 The licensee's assessment of the Technical Specification Improvement Project surveillance requirements documented in NRC Inspection Report 50-361/97-11; 50-362/97 11 did not include an assessment of surveillance requirements in the Offsite Dose Calculation Manual; however, the scope of this assessment was reasonable based on the specific issues that were documented in NRC Inspection Report 50-361/97-11; 50-362/97-11. Accordingly, the licensee did not identify the above procedural deficiency to implement the Offsite Dose Calculation Manual surveillance requirement during that assessmen 'The inspector verified that the licensee's corrective actions to revise the appropriate operating procedures to include the required verification and recording of dilution pump operation during liquid effluent operations were complete l Technical Specification 5.5.2.3, states, in part, that the radioactive effluent controls program shall be contained in the Offsite Dose Calculation Manual and shall be ]

q implemented by operating procedures. The licensee failed to establish an operating procedure to implement the Offsite Dose Calculation Manual 4.1.1.2 surveillance .

requiremen This non-repetitive, licensee identified and corrected violation of Technical Specificadon ;

5.5.2.3 involving the failure to establish an operating procedure to implement the surveillance requirement in Offsite Dose Calculation Manual 4.1.1.2 is being treated as a Non-Cited Violation, consistent with Section Vll.B.1 of the NRC Enforcement Policy (50-361/9808-01).

I L 1

t

---

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

.

-13-V. Manacement Meetinas X1 Exit Meeting Summary The inspector presented the results of the inspection to members of licensee management at the conclusion of the inspection on July 31,1998. The licensee acknowledged the findings presented. No proprietary information was identified.

i

l

f l

t I

!

l L__________________________.__ _ _ . _ _ _ _ . _ . - _ . . _ _ . . _ . - _ .

.

l

!

.

ATTACHMENT SUPPLEMENTAL INFORMATION 1 l

PARTIAL LIST OF PERSONS CONTACTED Licensee i

M. Bua, Chemistry Engineering Supervisor, Chemistry i R. Burton, Supervisor, Chemistry G. Cook, Supervisor, Compliance J. Demlow, Quality Assurance Engineer, Nuclear Oversight D. Dick, Effluents Supervisor, Chemistry G. Gibson, Manager, Compliance J. Gillard, Chemistry Technician, Chemistry E. Goldin, Supervisor, Nuclear Regulatory Affairs J. Henderson, Chemistry Technician, Chemistry J. Hirsch, Manager, Chemistry K. Hodges, Chemistry Instructor, Nuclear Training T. Kent, Technical Support, Chemistry R. Krieger, Vice President, Nuclear Generation F. Liu, Engineer, Station Technical S. Mahler, Engineer, Nuclear Regulatory Affairs L. McCann, Technical Support, Chemistry D. Nunn, Vice President, Engineering and Technical Services M. Orewyler, Supervisor, Maintenance K. Rauch, Supervisor, Operations Training A. Scherer, Manager, Nuclear Regulatory Affairs K. Sleek, Radwaste Operator, Operations P. Smith, Chemistry Technician, Chemistry C. Stinson, Supervisor, Nuclear Training K. Yhip, Engineer, Nuclear Regulatory Affairs NRC J. Sloan, Senior Resident inspector J. Russell, Resident inspector J. Kramer, Resident inspector LIST OF INSPECTION PROCEDURES USED IP 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring I

,

_______ _ _ _ _ _ __ _ _ _

.

.

i i-2- I LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED Opened 361/9808-01 NCV Missed Technical Specification and Offsite Dose Calculation Manual Surveillance Due to Procedural Omission

'

Closed 50-361/1998-006 LER Missed Technical Specification Surveillance Due to Initial Procedural Error 361/9808-01 NCV Missed Technical Specification and Offsite Dose Calculation Manual Surveillance Due to Procedural Omission LIST OF DOCUMENTS REVIEWED ORGANIZATION CHARTS Chemistry Department - June 1998 Operations Department - June 1998 CHEMISTRY TRAINING DOCUMENTATION Chemistry department training records

.

SO123-XXI 1.11.10 " Chemistry Training Program Description," Revision 6, April 15,1996 l

'

" Units 2 and 3 Nuclear Chemistry Training Qualification Guide," QM5700, Revision 9

" Nuclear Chemistry Technician Task Qualification Matrix," dated July 24,1998 l

Lesson Plan (CYO12) " Liquid Radwaste Treatment Program," Revision 0 i Lesson Plan (CYO15) " Wide Range Gas Monitoring (WRGM) System," Revision 2 i Lesson Plan (CYO20) " Process and Effluent Radiation Monitoring System (Units 2/3),"

Revision 3

!

Lesson Plan (CYO38) " Miscellaneous Liquid Waste System,'" Revision 3 Lesson Plan (CYO39) " Coolant Radwaste System," Revision 4 Lesson Plan (CYO40) " Gaseous Radwaste System," Revision 2 l

..

.

-3-Lesson Plan (CY151) " Evaluation of Unplanned Monitored Radioactive Gaseous Releases," Revision 1 Lesson Plan (CY157) " Liquid Release Permit Generation," Revision 3 Lesson Plan (CY158) " Gaseous Release Permit Generation," Revision 2 OPERATIONS TRAINING DOCUMENTATION Operations department training records

" Operations Crew Task Qualification Matrix" dated July 14,1998

" Units 2 and 3 Radwaste Operator Qualification Guide," 2JO202, Revision 4 Lesson Plan (2XRLO4) " Miscellaneous Liquid Radwaste System," Revision 3 Lesson Plan (2XRLOS) " Coolant Radwaste System," Revision 2 Lesson Plan (2XRLO6) " Gaseous Radwaste System," Revision 3 Lesson Plan (2XRLO7) " Radiation Monitoring System," Revision 3

,

Lesson Plan (2XRR07) " Release Permit /Offsite Dose Calculation Manual," Revision 1 QUALITY ASSURANCE DOCUMENTS Quality Assurance Master Audit Schedules for 1997 and 1998 San Onofre Topical Report SCE-1 A," Quality Assurance Program Description," Amendment 18, Change Notice 41, dated July 1996 Topical Quality Assurance Manual (TOAM), Revision 13, December 20,1996 SO123-XII-1 " Scheduling of Audits," Revision 4, October 3,1997 l

'

SO123 XII 18.15 " Nuclear Oversight Surveillance and Observation Program,"

Revision 2, March 31,1998 Self Assessments

" Technical Specification improvement Project Program Self Assessment," dated March 6,1998

"Self Assessment of the Units 2 and 3 Offsite Dose Calculation Manual Surveillance Requirements," conducted April through June 1998

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

.

'

.

Vendor Audits NUPIC Joint Quality Assurance Audit of Teledyne Brown Engineering-Environmental Services, I conducted August 26-30,1996 I

)

NUPIC Joint Quality Assurance Audit of NUCON International, conducted July 15-18,1997 PROCEDURES Chemistry Procedures SO123-Ill-4.1 " Operation and Calibration of Beckman LS6000 L.iquid Scintillation Counter ," Revision 3 SO123-lli-4. " Operation of the VAX/VMS Gamma Spectrometer," Revision 5 SO123-ill-5.1.23 " Units 2 and 3 Effluent Sampling and Analysis," Revision 18 SO123-ill-5.2.23 " Units 2 and 3 Liquid Effluent Sample Collection," Revision 9 SO123-lil-5.3.23 " Units 2 and 3 NMC Airborne Radioactivity Monitor Sample Collection,"

Revision 16 SO123-Ill-5.5.23 " Units 2 and 3 GA Airborne Radioactivity Monitor Sample Collection,"

Revision 11 SO123-ill-5.10 " Liquid and Gaseous Effluent Dose Determinations," Revision 8 SO123-lll-5.11.23 " Units 2 and 3 Liquid Effluent Releases," Revision 13 SO123-Ill-5.12.23 " Units 2 and 3 Gaseous Effluent Release Permit," Revision 11-3 SO123-Ill-5.23.23 " Units 2 and 3 Nuclear Data ND6685 Computer Operation for the Generation of Radioactive Effluent Release Permits," Revision 1 SO123-ill-5.24.23 " Units 2 and 3 Nuclear Data ND6685 Computer Operation for the Generation of Radioactive Effluent Release Reports," Revision 0 SURVEILLANCE TESTS Surveillance Operatina Instructions l

SO23-3-3.21 " Radiation Monitoring and Common Daily Surveillance - All Modes,"

Revision 9 l

- _ _ _ - _ _

.

.

-5-Radiation Monitorina Procedures SO23-XXV-4.12 " Condenser Evacuation System Loop 2/3RT-7818 Channel Functional Test," Revision 5 SO23-XXV-4.13 " Condenser Evacuation System Loop 2/3RT-7818 Channel Calibration," Revision 3 SO23-XXV-4.14 " Containment Purge / Plant Vent Stack Wide Range Gas Monitoring System Loop 3RT-7865-1 Channel Functional Test," Revision 4 SO23-XXV-4.15 " Containment Purge / Plant Vent Stack Wide Range Gas Monitoring System Loop 3RT-7865-1 Channel Calibration," Revision 4 SO23-XXV-4.16 " Liquid Radwaste Effluent Line Loop 2/3RT-7813 Channel Functional Test," Revision 1 SO23-XXV-4.17 " Liquid Radwaste Effluent Line Loop 2/3RT-7813 Channel Calibration,"

Revision 3 SO23-XXV-4.18 " Plant Vent Stack / Waste Gas Holdup System Loop 2/3RT-7808 Channel Functional Test," Revision 3 SO23-XXV-4.19 " Plant Vent Stack / Waste Gas Holdup System Loop 2/3RT-7808 Channel Calibration," Revision 2 SO23-XXV-4.22 " Neutralization Sump Discharge Radiation Monitor Loop 2/3RT-7817 Channel Calibration," Revision 2 SO23-XXV-4.23 " Turbine Plant Area Sump Radiation Monitor Loop 2/3RT-7821 Channel Calibration," Revision 4 SO23-XXV-4.42 " Turbine Plant Area Sump Radiation Monitor Loop 2/3RT-7821 Channel Functional Test," Revision 6 SO23-XXV-4.43 " Neutralization Sump Discharge Radiation Monitor Loop 2/3RT-7817 Channel Functional Test," Revision 3 SO23-XXV-4.44 " Steam Generator (E089) Blowdown Bypass Effluent Line Radiation Monitor Loop 2/3RT-6753 Channel Calibration," Revision 2 SO23-XXV-4.50 " Containment Purge Stack Radiation Monitoring System Loop 2/3RT-7828 Channel Functional Test," Revision 4 SO23-XXV-4.51 " Containment Purge Stack Radiation Monitoring System Loop 2/3RT-7828 Channel Calibration," Revision 1 SO23 XXV-4.59, " Steam Generator (E088) Blowdown Bypass Effluent Line Radiation Monitor Loop 2/3RT-6759 Channel Functional Test," Revision 2 SO23-XXV-4.60 " Steam Generator (E089) Blowdown Bypass Effluent Line Radiation Monitor Loop 2/3RT-6753 Channel Functional Test," Revision 2 e

!

_ _ _ _ - _ - _ _ _ _ _ ____-_____- _ _ _

.

E 6-SO23 XXV-4.62 " Steam Generator (E088) Blowdown Bypass Effluent Line Radiation Monitor Loop 2/3RT-6759 Channel Functional Test," Revision 2 instrumentation Procedures SO23-ll 8.489 "Radwaste Discharge Flow to Circulating Water Outfall 2/3FT 7643 Channel Functional Test," Revision 8 SO23-ll-8.48 "Radwaste Discharge Flow to Circulating Water Outfall 2/3FT-7643 Channel Calibration," Revision 2

,

SO23-II-8.464 " BPS Neutralization Sump Overboard Discharge Flow 2/3FT-3772 Channel Calibration," Revision 6 SO23-il-8.852 " BPS Neutralization Sump Overboard Discharge Flow 2/3FT-3772 )

Channel Functional Test," Revision 5

]

SO23-il-8,597 " Waste Gas Holdup System Flow Rate Monitor Channel Functional l Test," Revision 5 )

SO23-ll-8.59 " Waste Gas Holdup System Flow Rate Monitor Channel Calibration,"

Revision 1 SO23-II-9.670 " Steam Generator (E088) and (E089) Blowdown Flow 2FT-4055 and 3FT-4056 Channel Calibration," Revision 4 SO23-ll-9.712 " Steam Generator (E088) and (E089) Blowdown Flow 2FT-4055 and 3FT-4056 Channel Functional Test," Revision 1 MISCELLANEOUS DOCUMENTS Selected liquid radioactive waste batch release permits Selected waste gas decay and containment release permits l Effluent radiation monitor surveillance test records Engineered-safety feature air cleaning systems surveillance test records Annual Radioactive Effluent Release Reports - 1996 and 1997 i

" Units 2 and 3 Offsite Dose Calculation Manual," Revision 31, February 27,1998