IR 05000423/1985065

Insp Rept 50-423/85-65 on 851121-25 & 1112-15.No Violation or Deviation Noted.Major Areas Inspected:Preoperational Insp of Chemistry & Radioactive Effluent Control Programs, Including Organization & Staffing

ML20138M803
Person / Time
Site:	Millstone
Issue date:	12/17/1985
From:	Shanbaky M, Struckmeyer R, Weadock A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20138M785	List: IR 05000423/1985065 ML20138M779
References
50-423-85-65, NUDOCS 8512230167
Download: ML20138M803 (21)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

I Report N /85-65 Docket N License N CPPR-113 Category C licensee: Northeast Nuclear Energy Company P. O. Box 270 Hartford, Connecticut 06101 Facility Name: Millstone Nuclear Power Station, Unit 3 Inspection At:' Waterford, Connecticut Inspection Conducted: October 21-25 and November-12-15, 1985 Inspectors: 'f -

R. K. Struckmeyer, Radia gon Specialist

/A/d/F5 date'

[/ A. A: Weadock, Radiation Specialist

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Approved by: b ,. . Ir3 r~c - /2.!/7h[

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M. M. $3anbaky, Chief, PWR Radiation Safety Section

/ K dater Inspection Summary:

Inspection on October 21-25 and November 12-15, 1985 (Report No. 50-423/85-65)

Areas Inspected: Routine, announced, pre-operational inspection of the chemistry and radioactive effluent control programs. Areas' reviewed included: organization and staffing, training and qualification program, facilities and equipment, radiological confirmatory measurements, and plans and procedures. The inspection involved 100 inspector hours on-site by two NRC reglor based inspector Results: No violations were identifie fok D G

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DETAILS Individuals Contacted (1) J. Crockett, Unit 3 Superintendent M. Brown, I&C Supervisor, Unit 3 M. Ciccone, Startup Engineer, NNEC0 F. Chamberland, Startup Engineer, NNECO J. Chunis, Startup Engineer, NNECO (1) R. Cikatz, QC Engineer, NNECO (1) G. Closius, QA/QC Supervisor, NNECO (2) R. Enoch, Assistant I&C Supervisor R. Grebasch, Startup Engineer, NNECO T. Lane, Startup Engineer, S&W (1) R. Langer, Assistant Chemistry Supervisor, Unit 3 (1) J. LaWare, CQA Engineering Technologist, NUSCO C. Mallory, Chemistry Trainer, NUSCO M. Manolakis, Unit 3 I&C Trainer, NNECO (1) D. Miller,'Startup Manager, NNECO C. Myers, Nuclear Containment Systems, In (1) (2) L. Nadeau, Assistant Project Engineer, NUSCO J. Niemeyer, Air Balance Test Engineer, S&W R. Olsen, I&C Engineer, NUSCO (1) V. Papadopoli, CQA Supervisor, NUSCO F. Perry, Assistant Radiation Protection Supervisor, NNECO D. Powers, Startup Engineer, S&W L. Rayburn, Associate Scientist, RAB, NUSCO D. Robinson, I&C Engineer (1) R. Sachatello, Radiation Protection Supervisor D. Scace, Startup Engineer, NNECO (2) A. Stengel, Startup Engineer, NNEC0 W. Thomas, Thomas Young Associates H. Thompson, Startup Engineer, NNEC0 J. Townsend, Instrument Specialist (1) J. Waters, Chemistry Supervisor (1) Indicates those present at final exit meeting on November 15, 1985.

(2) Indicates those present at exit meeting on October 25, 1985.

2. Status of Previously Identified Items (0 pen) Inspector Followup Item (50-423/85-19-01): Status of Radiation Monitoring System (RMS). All monitors have been turned over, and all but two have been field tested (exceptions are 3RMS*RE04 and 3RMS*RE05, Containment High-Range Monitors). Phase II testing is in progress, involving communications capability between monitors and RMS compute This capability is not needed for fuel load. Monitor status is given in Attachment I to this report; those required for fuel load (as identified by the licensee) are identified by the letter "F" in the second column of the table, i

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(0 pen) Inspector Followup Item (50-423/85-19-02): Status of RMS Surveil-lance Procedure and Generic Procedure development. All surveillance procedures pertaining to calibration and operability testing of RMS monitors have been written and PORC approved. The status of these pro-cedures is indicated in Attachment II. Procedure numbers 3449 001, 3449 D11, 3449 F01, 3449 Fil, 3450 001, and 3450 011 have been deleted from this list since last update. The monitors covered by these procedures are not covered by Technical Specifications, therefore, surveillance procedures are not required. The calibration and operability of these monitors will be covered by I&C procedures as noted in the tabl The status of RMS generic procedures (I&C procedures) is given in Attach-ment III. A licensee representative stated that these procedures would be finalized and approved prior to commercial operation (0 pen) Inspector Followup Item (50-423/85-42-01): Training of NNECO chemistry technicians, and training and qualifications of contractor technicians. The inspector reviewed the training program for NNECO chemistry technicians, including lesson plans, course materials, training conducted through mid-October, and plans for continuing training. The licensee has not yet finalized plans concerning train-ing for contractor technicians. These areas will remain open pending further NRC ceview. See Section 3 of this repor .

(Closed) Inspector Followup Item (50-423/85-42-02): Training and Quali-fications of NNECO and Contractor I&C Technician The inspector reviewed training plans and selected personnel records. These records indicate that the licensee has adequate controls to ensure that its I&C technicians have the appropriate qualifications, and that training will be provided to technicians. See Section 3 of this repor (0 pen) Inspector Followup Item (50-423/85-42-03): Status of liquid and gaseous radwaste systems. The inspector completed walkdowns on the Liquid Waste System (LWS), the Boron Recovery System (BRS), the Condensate Demin-eralizer Clean-up System (CND), and the Gaseous Waste System (GWS), as well as those ventilation systems for which HEPA and charcoal filtration is required, and verified that major components of these systems (except HEPA and charcoal filters) have been installed as described on the Piping and Instrument Diagrams in the FSA Installation and testing of filtra-tion components (HEPA, charcoal, and pre-filters) will be conducted on an as-needed basis (i.e., for initial criticality, power ascension, etc.).

The Control Room Emergency Ventilation system filters have been installed and tested, as required for fuel load. Testing (Phase III) has been con-ducted on the Primary System Sampling Station, as required for fuel-loa A design deficiency (DDR 759) identified during testing, regarding an ina-bility to obtain steam generator samples when at low pressure due to pres-sure drop caused by restricting orifices in sample lines, was resolved subsequent to the conclusion of this inspectio The status of systems will continue to be followed in future inspections of this are F'

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(Closed) Unresolved Item (50-423/85-42-04): Adequacy of Radiation Monitoring System (RMS) calibration procedures. The inspector reviewed additional information provided by the licensee (details, Section 4). The proper calculation and application of a Radiological Engineered Calibration Factor (RECF), which is updated for each monitor at each calibration, provides the necessary link to the original factory calibratio In addi-tion, the correct operation of each detector is verified by checking its high voltage threshold, and by the use of radioactive sources to check the linearity of respons (0 pen) Inspector Followup item (50-423/85-42-05): Status of chemistry analytical and surveillance procedures. The inspector determined that chemistry surveillance procedures required for fuel load have been written and PORC approve Two surveillance procedures (Nos. 3866 and 3822) were identified by the licensee as required for initial criticality rather than for fuel load. These pertain to noble gas release rate control and moni-toring, and to offsite dose calculation per the REM 0DCM, respectivel The responsibility for procedures pertaining to Radiological Environmental Monitoring was transferred to the corporate office (NUSCO). The licensee reviewed its chemistry analytical procedures to determine which are needed for fuel load and which are needed in later phases of startup. Within the former group, the licensec stated that all procedures have been p0RC ap-proved. The status of procedures not needed for fuel load, and not yet approved, will be reviewed in a future inspectio (0 pen) Inspector Followup Item (50-423/85-4; -06): Status of Phase II startup procedures for liquid and gaseous cacy- te systems and ventilation systems. The Liquid Waste System (LWS), Boron covery System (BRS), and Gaseous Waste System (GWS) are not required to be fully tested and opera-tional until the power-ascension phase of startup; therefore, testing of these systems was not reviewed. Draft copies of the Phase II test procedures were reviewed and found to be adequate. The licensee stated that these procedures have received PORC approval. The status of these procedures, including test results, will continue to be followed in a future inspectio (0 pen) Inspector Followup Item (50-423/85-42-07): Status of filtration system (HEPA and charcoal) surveillance test procedures. Testing of the Control Room Emergency Ventilation (CREV) System filtration components is required for fuel load. The test procedure was reviewed and a portion of the test was witnessed by the inspector; all of the necassary tests have been completed and are undergoing internal review. Test procedures for other filtration systems are similar to the procedure for the CREV. These procedures and the test results will be reviewed in a future inspectio . Organization and Staffing The inspector reviewed, in P.eport No. 50-423/85-42, the licensee's organi-zation with respect to staffing and management structure in the areas of chemistry and radioactive effluent control. That review included qualifi-cation and training of technicians in the licensee's Chemistry Department and in its Instrumentation and Controls (I&C) Departmen f-

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The inspectors reviewed the training program for NNECO chemistry techni-cians, includf ag lesson plans, course materials, training conducted through mid-October, and plans for continuing training. Preliminary testing indicated that refresher training was necessary for some techni-cians in nuclear physics, math, and/or chemistry. After this training, the attendees were retested. Three did not pass; of these, two had been unable to attend the refresher training. These three individuals will be provided additional refresher training and testing. The licensee had not decided what action would be taken if any technicians continued to fall

.the tests. This area will be reviewed in a future inspectio The-licensee stated, in a telephone conversation with the inspector, that its contractor technicians meet the qualification requirements of ANSI N 18.1; however, the inspector has not reviewed the documentatio In addition, the licensee has not yet finalized plans concerning training of-contractor technicians. These areas will remain open pending further NRC .

review (50-423/85-42-01).

The inspector reviewed training plans and selected I&C personnel record Periodic training will be provided to NNECO I&C technicians; however, details of the training program have not been settled upon. It will include.both technical and plant related (e.g. systems and procedures)

materials. During a previous inspection (see Report No. 50-423/85-42)

I&C management indicated that the following criteria would be used to

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screen contractor technicians:

a) technicians would require a minimum of two years technical experience not necessarily nuclear-related, with a preference for those over five years experience, and b) technicians would be required to pass a written examination covering technical areas related to the work of the departmen The inspector reviewed personnel files of selected I&C contractor techni-cians and verified that all technicians met the experience criteria and had received the licensee's written examination. The inspector noted that besides being used as a hire /no-hire criterion, the exam was used to iden-tify weak areas in the technician's experience and knowledge. Assignment of contractor technicians to one of the I&C department's working groups (Analog, Digital, or Analog and Digital) was made partly on the basis of exam performanc . Facilities and Equipment The inspectors reviewed the status of the liquid and gaseous radwaste systems and the primary and secondary system sampling stations with respect to the FSAR design criteria for these systems. This review included walkdowns of the major components of these systems. With regard to the Radioactive Liquid Waste System, a virtually complete

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I walkdown was performed, including all tanks, valves, pumps, filters, i radiation monitor, and piping connections between components. All major opponents of the Boron Recovery System, the Condensate Demin- .

eralizer Liquid Waste System and the Gaseous Waste System were examined, as wel!.

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The inspector noted that most Phase I tests and the majority of Phase II tests concerning liquid and gaseous effluent systems have been complete There is just one Phase II test procedure covering all filtration system component (HEPA and charcoal) testing; at the conclusion of this inspection, only the Control Room Emergency Ventilation filtration components (HEPA and charcoal) had been tested. Installation and testing of filtration components for the remaining systems required by Technical Specifications will be conducted on an as-needed basis (i.e., initial criticality, power ascension,etc.). The status of tests will continue to be followed in

' future inspections of this area (50-423/85-42-03). ,

4.1 Radiation Monitoring System The Radiation Monitoring System (RMS) was reviewed in NRC Inspection Report 85-19, which included a brief system description and reported the status in terms of operability and testing of equipment, and development of procedures. The licensee's Instrumentation and Control (I&C) group has responsibility fo** the testing, calibration,

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and maintenance of the RMS, and for development of surveillance procedure The purpose of this review of the RMS was to update the status of the licensee's progress in making the system operational, and to review monitor calibration procedures and dat O g .oility Selected process and effluent radiation monitors were examined with i regard to their locations, operability, and appropriate connections to the systems to be monitore As of November 20, 1985, the operational status of the RMS was as depicted in Attachment 1. Most process, effluent, and area radiation monitors have been installed and tested individually. The integrated system test (Phase II) is in progress. The inspectors stated that the status of the RMS would again be examined during a subsequent inspection (50-423/85-19-01).

Calibration The licensee is currently using a secondary transfer source calibra-tion technique to calibrate the RMS. This technique is recommended

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by the RMS vendor (KAMAN) and was previously reviewed and described in NRC Inspection Report 85-42. Inspector concerns with the cali-bration technique identified during that inspection included:

1) use of a single radionuclide source during field calibrations to link back to a generic, multi-isotope energy response curve, and 2) lack of acceptance criteria to evaluate detector response to the transfer sourc Inspector effort during this inspection was directed towards the further investigation and resolution of the above concerns. Review in this area included:

1) review of vendor-supplied isotopic energy-response curves, 2) discussion with engineering personne1'concerning the calculation of calibration factors linking detector response to the generic energy and efficiency calibration to ensure energy response stability of the system, and 3) discussion with I&C supervisory and vendor personnel concerning detector respons The inspector determined the licensee's current technique is adequate for performing detector calibrations for the RMS. The proper calcu-lation and application of a Radiological Engineered Calibration Factor (RECF), updated for each monitor at each calibration, relates current monitor response to the response at the original primary calibratio This provides an adequate link back to the original energy response curve. Performance of a linearity check and the establishment of high voltage thresholds for the detectors provides an adequate check of detector respons . Plans and Procedures The inspectors reviewed the licensee's procedures for pre-operational testing of liquid and gaseous radwaste systems, ventilation systems, and radiation monitoring system. The inspectors noted that virtually all procedures for individual component (Phase I) testing had been written and approved. Procedures for integrated system (Phase II) testing have been written and approved for the following systems: primary system sampling station, gaseous redwaste processing system and ventilation systems (for those which may contain radioactivity during normal operations), liquid radwaste system, charcoal and HEPA filter tests, and radiation monitoring syste Approxi,rately 85 percent of chemistry procedures, including all of those required for fuel load have been written and approved. Chemistry is also responsible for developing and implementing 27 Surveillance Procedures; at the conclusion of this inspection, all but two (which are not required for fuel load) had been written and PORC approved.

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The inspectors reviewed the current status of Radiation Monitoring System (RMS) surveillance procedures, for operation, testing, and calibration of RMS units that are expected to be addressed by Technical Specification Attachments 2 and 3 depict the status of these procedures as of November 15, 198 The status of the licensee's procedures will continue to be followed in subsequent inspections of this area; including:

Chemistry analytical and surveillance procedures (50-423/85-42-05).

RMS generic (I&C) procedures (50-423/85-19-02).

• Phase II startup procedures for liquid and gaseous radwaste systems and ventilation systems (50-423/85-42-06).

Filtration system (HEPA and charcoal) surveillance testing (50-423/85-42-07).

6. Capability Test Rasults The licensee maintains the capability for analysis by gamma spectroscopy in both its chemistry and its health physics laboratorie There are three such systems available in chemistry, and two in health physic The inspector submitted test samples to these laboratories in order to evaluate the licensee's capability to measure radioactivity in effluent and in plant sample The test samples consisted of a simulated particu-late filter and a spiked charcoal cartridge, both of which are representa-tive of samples the licensee would encounter during operation. The test samples were analyzed by the licensee using the licensee's normal methods and equipmen The results of the test sample measurements comparison indicated that all of the measurements were in agreement under the criteria used for inter-comparing results, listed in Attachment I The intercomparison results data are listed in Attachment Additional intercomparison data will be obtained for evaluation of the licensee's capability to measure radioactivity in liquid samples. These samples will be prepared by the NRC reference laboratory (the DOE Radio-logical and Environmental Sciences Laboratory) and sent to the license One sample, containing radioactivity detectable by gamma spectroscopy, will be analyzed by the licensee's chemistry and health physics laboratories. A second sample, containing tritium, strontium, and mixed alpha emitters, will be forwarded to the licensee's vendor laboratory for analysis. The results of these analyses will be sent to the NRC Region I office as they are obtained by the licensee, and will be documented in a future inspection of this area (50-423/85-65-01).

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, Laboratory quality Control Program

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l 6-The chemistry laboratory QC program is detailed in Procedures CP 3800,

" Chemistry Quality Assurance Program," and CP 3800 B, "QA Control Chart Preparation." Procedure CP 3800 addresses equipment calibration, intra-

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laboratory analyses of dukiicate and spiked samples, interlaboratory analyses of. split water & mples, and preparation of reagent,and standard sMutio',is for QA analyse Procedure CP 3800..B discusses the method of preparing quality control charts for various types of chemical p measurement <

The inspector noted that the licensee's quality assurance procedure con-tained no reference to a quality control program for its< vendor laboratory, in which QC samples (spikeh splits, duplicates, etc.) are prepared by the licensee and sent to therverdor laboratory for analysis. The licensee stated that such a program is maintained by the Units 1 and 2 chemistry laboratory, and that the Unit 3 laboratory uses the same vendor. The

, inspector stated that the Unit 3' quality assurance procedure should referenc'a this vendor QC prograni.. The licensee agreed to reference this program pnd stated tnat any prib>.as with the vendor laboratory would be communic eed to the Unit 3 laboratory tia the Millstone site Chemistry

. Shperviso/. This will be reviewed in a future inspection (50-423/85-65-02).

e, o Health Physin V

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" Health Physics Spectrometer Instrumentation," and ndted that it contains instructions for daily performance checks, and-instructions for energy and efficiency calibration. The procedure does not provide for the preparation of QC kharts. The inspector stated that such charts should be utilized c,

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because of the additio,a1 benefits \the.p hfford with regard to displaying

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detector trends; e.g.l; bias (most W 2.11 results above or below the known val'2) and drift (results tend to %ove steadily, up or down over a period of time). Control charts enable tne operator to recognize potential problems before the instrument 6t1 outhf control, and, therefore, take steps to correct the problem. The licensee stated that the next revision of its proced_upe will specify that control charts be established and main-tained for it's gamma spectroscopy systena (50-423/85-65-03). Exit Interview

l w The inspector eet with the licensee representattves (denoted in j Paragraph 1) at the tonclusion of the inspections on October 25 and l November 15, 1985.Vand summarized the purpose and sc' ope of the inspec-

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tions and the inspection findings. The licensee agreed to perform the i

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analyses listed in Faragraph 6 and report the results to the NR ,; . ,

j At no time during these inspections was w'itten material prnvided to the l licensee by the inspecto . L.

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ATTACHMENT I Radiation Monitoring System Status Instrument Number Mile- Field Communications (Mark No.) stone Tested Loop Established Comments Ventilation / Gas Monitors 3HVRRE10A/B* F (* Testing complete, eval-( uation of results in ( progres HVRRE19A/B* F (* Check source response ( malfunction under ( investigatio HVRRE11A/B C X X Flow adjustment required 3HVRRE12A/B C X X Flow adjustment required 3HVRRE13A/B C X X Flow adjustment required 3HVRRE14A/B C X X Flow adjustment required 3HVRRE15A/B C X X Flow adjustment required 3HVRRE16A/B C X X Flow adjustment required 3HVRRE17A/B C X X Flow adjustment required 3HVRRE18A/B C X X Flow adjustment required 1HVCRE91A/B C X X 3CMSRE22A/B* P X X 3HVZRE09A/B C X X Monitor reads too high 3HVQRE49A/B* F X X 3HVCRE16A/B* F X X

• Category 1E Monitors r

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Radiation Monitoring System Status Instrument

' Number Mile- Field Communications (Mark No.) stone Tested Loop Established Comments Liquid Process Monitors 3CHSRE69 C X X

'3CCPRE31' C X t X s

i 3CNARE47 C X X 3DASRE50 F X X Q,d 3LWSRE70 F X X ..

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'3LWCRE65 F A X 3CNDRE07 F X X 3SSRRE08- F X

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35WPRE60A/B 'C X X 3GWSRE48 C X X lb -3ARCRE21- C X X 3MSSRE75- C X X 3MSSRE76 C X~ X 3MSSRE77 C X X 3MSSRE78 C X X 3MSSRE79 C X v 5-1 b,-

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ATTACHMENT I (Continued)

Radiation Monitoring System Status Instrument Number Mile- Field Communications

~(Mark No.) stone Tested Loop Established Comments Area Monitors 3RMSRE01- C X X 3RMSRE02 C X X 3RMSRE03 C X X 3RMSRE06 C X X 3RMSRE07 C X X 3RMSRE08 C X X 3RMSRE09 C X X 3RMSRE10 C X X 3RMSRE11' C X- X 3RMSRE12 C X X

~3RMSRE1 C X X

!3RMSRE14 C X X

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3RMSRE15 C- X X 3RMSRE38 C X X 3RMSRE52* C X X 3RMSRE16 C X X

. 13RMSRE17 C- X X

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-* Category IE Monitors .

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1 ATTACHMENT I (Continued)

Radiation Monitoring System Status Instrument Number Mile- Field Communications (Mark No.) stone Tested Loop Established Comments Area Monitors 3RMSRE18 C X X 3RMSRE19 C X X 3RMSRE20 C X X 3RMSRE21- C X X 3RMSRE22 'C X X 3RMSRE24 X X 3RMSRE25 C X X 3RMSRE28 C X X 3RMSRE29 C X X

~3RMSRE31 C X X 3RMSRE32 C X 'X 3RMSRE33 C X -X 3RMSRE34 C X X 3RMSRE35 C X RMSRE3 C X X 3RMSRE37 C X X L

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ATTACHMENT I (Continued)

Radiation Monitoring System Status Instrument

. Number- Mile- Field Communications (Mark No.) stone Tested Loop Established Comments Area Monitors

'3RMSRE04* P ( Installed and calibrated; (

3RMSRE05* P ( Cable check and surveil-( lance incomplete 3RMSRE41* F ( Testing complete (11/19);

( evaluation of results in

- 3RMSRE42* F ( progress Milestone:

F = Fuel ~ 1oad P = Post-core hot functional ~

C = Commercial operation t

• Category 1E Monitors

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ATTACHMENT II RMS Surveillance Procedure Summary Procedure PORC Number Monitor Identification Approval Comments

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3449A01 3HVR-RE10A/B Vent Part/ Gas 10/25/85 66'6" Aux. Bldg. Cal. Pro A11 3HVR-RE10A/B Vent Part/ Gas 10/19/85 66'6" Aux. Bldg. Oper. Test 3449801 3HVR-RE19A/B SLCRS Part/ Gas 11/01/85 Cal. Pro .3449B11 3HVR-RE19A/B SLCRS'Part/ Gas 10/29/85 Oper. Test 3449C01 3 CMS-RE22A/B CTMT Atmo /29/85 Part/ Gas Cal. Proc.-

3449C11 3 CMS-RE22A/B CTMT Atmo /29/85 Part/ Gas Oper. Test 3449D01 '3SWP-RE60A/B CTMT Recir Deleted Changed to I&C Cooler'Syc. Water Outlet Proc. No. 3490 B12 Cal. Pro D11 35WP-RE60A/B CTMT Recir Deleted t

Cooler Svc. Water Outlet Oper. Test

'3449E01 3RMS-RE41/42 Fuel Drop Monitor 10/29/85 51'4" Cal. Pro E11 3RMS-RE41/42' Fuel Drop Monitor 10/29/85 51'4" Oper. Test 3449E21 Fuel Pool Storage Criticality 09/03/85

~ Monitor Cal. Pro '

3449E31 Fuel Pool Storage Criticality 09/06/85 Monitor Oper. Test 3449F01 3HVZ-RE09A/B Recom. Cub. A/B Deleted Changed to I&C

~Exh. 7'6" Cal. Pro Proc. No. 3490 B05 3449F11 3HVZ-RE09A/B Recom. Cub A/B Deleted Exh. 7'6" Oper. Test

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ATTACHMENT II (Continued)

RMS Surveillance Procedure Summary Procedure PORC Number- Monitor Identification Approval Comments 3449G01 3HVC-RE16A/B Control Bld /11/85 Inlet Cal. Pro G11 3HVC-RE16A/B Control Bld /03/85 Inlet Oper. Test 3449H01 3RMS-RE04/05 Cont. HR Inte /25/85 51'4" CTMT Cal. Pro H11 3RMS-RE04/05 Cont. HR Inter 09/20/85 51'4" CTMT Oper. Test 3449J01 3HVQ-RE49 ESF Part & Gas Ra /05/85'

Monitor Cal. Pro J11 3HVQ-RE49-ESF Part & Gas Ra /29/85 Monitor Oper. Test 3450D01 3 MSS-RE75, 76, 77, 78 Main St Deleted ' Changed to I&C

' Rel . Line A-D Cal . Pro Proc. No. 3490 B08 3450011 3 MSS-RE75,-76,.77, 78 Main St Deleted Rel. Line A-D Oper. Test 3450E01. '3 MMS-RE79 Turb. Drv. Aux. Fd Deleted Changed to I&C Pump Dsch.-Cal. Pro Proc. No. 3490 808 3450E11 3 MMS-RE79 Turb. Drv. Aux. Fd Deleted

. Pump Dsch. Oper. Test 3450F01 3CND-RE07. Waste Neut. Sump Ra /23/85 Monitor Cal. Pro F11 3CND-RE07 Waste Neut. Sump Ra /13/85 Monitor Oper. Test

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3450G01 3DAS-RE50 Turb. Bldg. Floor 09/10/85 Drains Rad. Monitor Ca Pro G11 3DAS-RE50 Turb. Bldg. Floor 09/13/85 Drains Rad. Monitor Ope Test

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ATTACHMENT II (Continued)

' RMS Surveillance Procedure Summary

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Procedure . PORC Number Monitor Identification Approval Comments 3450H01 3LWS-RE70 Liquid Waste Ra /23/85

Monitor Cal. Proc.

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3450H11 3LWS-RE70 Liquid Waste Rad - 09/17/85 Monitor Oper. Test 3450J01 -3LWC-RE65 Regen. Evap. Ra /23/85

' Monitor Cal. Pro J1 ~' 3LWC-RE65 Regen. Evap. Ra /13/85

. Monitor Oper.-Test 3450K01' 3SSR-RE08 S/G Blowdown Ra /23/85 Monitor Ca K11 3SSR-RE08 S/G Blowdown Ra /05/85 Monitor Oper. Test

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3450L41 - T/B Floor Drains, Regen. Eva . 11/19/85

.and S/G Blowdown Source Check

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ATTACHMENT III RMS Generic Procedure Summary l

Generic I&C N Procedure Monitor (GPIC) N Identification Status / Comment 20.01 3490B01 Kaman_ Science (KMG-HRN) Radiation Approved * Rev. O Monitor 20.02 3490B02 Kaman Science (KMG-HRH) Radiation Rev. O in Typing Monitor 20.03 3490B03 Kaman Science (KMPG) Radiation Approved * Rev. O Monitor 20.04 3490B04 Kaman Science (KML) Radiation Approved * Rev. O Monitor Draft-Rev. 1~

20.05 3490B05 Kaman Science (KMG) Radiation Draft Rev. O Monitor to Author for Corrections 20.06 3490B06 Kaman Science Hydrogen Vent Draft Rev. O Monitor -in Review 20.07 3490B07 Deleted 20.08 3490B08 Kaman Science (KMA-HR) Radiation In Review Monitor

.20.09 3490B09 Deleted 20.10 3490816 Kaman Science (KMA) Radiation Approved * Rev. O Monitor 20.11 3490B11 Kaman Science Fuel Failure Monitor In Typing 20.12 -3490812 Kaman Science Service Water In Review Effluent Monitor 20.13 ECl-4 Eberline Radiation Monitor In Development

• Approval of these procedures is by the I&C Department Supervisor and the Startup Manage _

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ATTACHMENT IV Criteria for Comparing Analytical Measurements This attachment provides criteria for comparing results of capability tests and verification measurements. The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this progra In these criteria, the judgement limits are variable in relation to the com-parison of the NRC Reference Laboratory's value to its associated uncertaint As that ratio, referred to in this program as " Resolution," increases, the acceptability of a licensee's measurement should be more selective. Conversely, poorer agreement must be considered acceptable as the resolution decrease Resolution Agreement

<3 0.4 - .5 - .6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.80 - 1.25

>200 0.85 - 1.18 t

+. .

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. ATTACHMENT V-s Cacaollity Test Re4ults - Chemi st ry Licensee Results *

lsotope NRC Value * Resolution Chem. Det. 1 Ratio ** Chem. Det. 2 Ratio ** Chem. Det. 3 Ratio **

- Particulate Filter Ce-144' (3.4610.02)E-02 173 (3.4310.10)E-02 0.99 (3.6110.08)E-02 1.04 (3.6010.10)E-02 1.04 Cs-137 (1.5010.02)E-02 75- (1.4910.02)E-02 0.99 (1.5610.02)E-02 1.04 (1.6110.02)E-02 1.07 Mn-54 (1.4710.02)E-02 74 (1.5210.04)E-02- 1.03 (1.5510.04)E-02 1.05 (1.5310.04)E-02 1.04 Co-60' (2.6810.02)E-02 134 (2.6510.03)E-02- 0.99 (2.9210.03)E-02 1.09 (2.8310.03)E-02- 1.0 Cha rcoa l Ca rtridge Cd-109 (3.4210.05)E-02 68 Not Detected + (3.910.2)E-02 1.14 v+ Not Detected +

Co-57 (9.8010.12)E-04 82 (8.211.2)E-04 0.84 (1.110.2)E-03 1.12 (1.0710.17)E-03 1.09 Ce-139 (5.1810.10)E-04 52 Not Detected + Not Detected + Not Detected +

Cs-137 (9.7410.05)E-03 195 (8.8410.12)E-03 0.91 (1.0210.01)E-02 1.05 (1.0010.01)E-02 1.03 Co-60 (9.8410.05)E-03 197 (9.3310.17)E-03 0.95 (1.1110.02)E-02 1.13 (1.0210.02)E-02 1.04 Notes:

1. Value given in total microcuries or isotope 'in sample

1. • Ratio of licensee value to NRC value

+ Nuclide not contained in licensee's isotopic library for charcoal cartridge sample

++ Alternate isotope library used for this analysis

,

~

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., - > ;_ '

l  : ATTACHMENT V (Continued)

Capability Test Results - Health Physics Licensee Results *

Isotone NRC Value * Resolution H. P. Det. 1 Ratio ** H. P. Det. 2 Ratio **

s Pa rticulate Filter .

' Ce-144 (3.4610.02)E-02 173 (3.8710.11)E-02 1.12 (3.8210.13)E-02 1.10 Cs-137 (1.5010.02)E-02 75 (1.5610.02)E-02 1.04 (1.5410.02)E-02 1.03 Mn-54 (1.4710.02)E-02 74 (1.6610.05)E-02 1.13 (1.6010.05)E-02 1.09 Co-60 (2.6810.02)E-02 13 (3.0210.03)E-02 1.13 (3.1610.03)E-02 1.18 l Cha rcoa l Ca rt ridge Cd-109 (3.4210.05)E-02 68 (2.810.1)E-02 0.82 (4.210.2)E-02 1.23

. Co-57 (9.8010.12)E-04 82 (8.711.0)E-04 0.89 (9.912. )E-04 1.01 Ce-139 (5.1810.10)E-04 52 <2.7 E-03 <4.2 E-03 Cs-137 ,(9.7410.05)E-03 195 (8.210.1)E-03 0.84 (1.0310.01)E-02 1.06 Co-60 -(9.84to.05)E-03 197 (8.910.2)E-03 0.90 (1.110.02)E-02 1.12 Notes:

1. Value given in total microcuries of isotope in sample

• • Ratio of licensee value to NRC value

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