ML20049K063

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Forwards Info Requested at 820129 Exit Interview Re Radiation Monitoring Sys Design,Training & QA Program
ML20049K063
Person / Time
Site: San Onofre 
Issue date: 02/04/1982
From: Ray H
SOUTHERN CALIFORNIA EDISON CO.
To: Wenslawski F
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML20049K043 List:
References
NUDOCS 8203290362
Download: ML20049K063 (18)
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{{#Wiki_filter:F.>.. DESICIIATED ORIGIIIAL g Certified By bk Southern California Edison Conhany g5 S AN ONOFRE NUCLE AR GENER ATING STA TION P.O. B O X f28 S AN C LEMENT E, C ALIFORNI A 92472 .. H. 8. R A Y ST A TION M AN Aet n (7841 4,2-7700 February 4,1982 U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 Attention; Mr. Frank Wenslawski Dear Sir;

SUBJECT:

Information Committed to be provided Region V as a result of the January 29, 1982, Exit Interview by Messrs. Wenslawski and Cillis By letter dated February 1,1982 (same subject), we forwarded four of ten specific items of information enumerated during the January 29, 1982 exit interview concerning the Region's preoperational inspection of the Health Physics inspection modules for San Onofre Unit 2. Those four items were identified as Items 3,4,6 and 7 at the exit interview and in Enclosure (1) to the February 1,1982 letter. Item 5 was also partially responded to by the February 1,1982 letter and item 1 has been provided to the Region by copy of Mr. K.P. Baskin's letter to Mr. Miraglia dated February 3,1982. This letter provides additional information identified during the January 29, 1982 exit interview as follows: provides information identified during the January 29, 1982 exit interview as Item 2. provides the balance of information identified during the January 29, 1982 exit interview as Item 5 not provided by the February 1,1982 letter. l provides information identified during the January 29, 1982 exit interview as Item 7. ' provides information identified during the January 29, 1982 exit interview as Item 8. ,;,g , provides information identified during the January 29, 1982 exit interview as Item 10. i /C *"'"d %' 033in l GS* th--*:s $NCLON8b .5 8203290362 820302 / PDR ADOCK 05000361 l 0 PDR

O U.S. Nuclear Regulatory Commission Page 2 At your request, the schedule for completion of enhanced calibration of process and effluent monitors, as discussed as part of Item 9, Enclosure (7) of the February 1,1982 letter will be provided on February 5,1982. If you have any questions concerning the information forwarded by this letter, or my previous letter of February 1,1982, or you require additional information, please let me know. [B.RA H. Enclosure cc: A.E. Chaffee (U.S. Resident Inspec' tor San Onofre Unit 2) t l lr

Enclosure I NRC Item 2 W is paper will discuss design considerations for the San Onofre 2 & 3 Gaseous Process and Effluent Radiation Monitoring System. As discussed in FSAR section 11.5.2, the principles and methods of ANSI N13.1-1969, " Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities", was used in the design of the gaseous process and effluent radiation monitors listed below: a) Gaseous Monitors or Monitors not Sampling fran Ducts 1) Containment Airborne Monitors (RP-7804-1, RT-7807-2) 2) Waste Gas Healer Monitor (2/3 RT-7814) 3) Condensor Air Ejector Gas Monitor (RT-7818) b) Isokinetic Monitors 1) Plant Vent Stack Airborne (2/3 RT-7808) 2) Radwaste Disposal Area Vent (2/3 RP-7809) 3) Fuel Handling Vent Airborne Monitor (RT-7822-1, RT-7823-2) 4) Control Room Airborne (2/3 RT-7824-1, 2/3 RP-7825-2) 5) Condensor Air Ejector Wide Range Monitor (RE-7870-1) 6) Containment Purge and Plant Vent Stack Wide Range Switchable (RE-7865-1) he monitor and sample line design also had to consider other factors. %ese factors included: 1) Incating mnitors in low radiation areas so that background effects would be minimized during normal plant operation. 2) Incating mnitors in an environment (usually inside a building) so that their performance would not be degraded due to harsh environments. 3) locating monitors in a" area accessable for necessary maintenance and other operations keeping radiation exposures as low as reasonably achievable. 4) Post-accident dose and access requirements for monitors required to function following a postulated accident. n

NRC Item 2 , 2-As discussed in Appendix A of ANSI N13.1, cmpromises between the best location for sampling frm a technical standpoint, and one that meets other desian requirements were made. An estimate as to the magnitude of the sampling error was made using the guidance of Appendix B of ANSI N13.1. We selection of sampling position and sample line design considers the type of monitor being used along with its intended function. %e waste gas header nonitor (2/3 RT-7814) and condensor air ejector gas nonitor (RT-7818) does not contain any device for measuring or obtaining iodine and particulate samples. We waste cas discharge line is frm the waste gas S cay tanks whig e ng mally stagnant for three to six months. As a result there w ,$e, particulate activity in the waste gas discharge line at the time of release. W e plant vent stack airborne monitor which smples the final release path is equipped with iodine and particulate sample capability. Similarly for the condensor air ejector, nealigible particulate and iodine activity will be present due to the scrubbing effect of the steam jet air ejector and main condensor design. Particula

  • and iodines will be removed frm the wide range gas monitor at the san, e conditioning skid, thus the smple lines downstream of the sample mndt ioning skid do not consider particulate and iodine deposition.

The contaiment airborne monitors (RT-7804-1, RT-7807-2) do not sample a flowing airstream; rather, they sz.nple the containment atmosphere. %e sample points for these two monitors are located inside containment in order to provide a representative sample of the containment atmosphere. To ensure representiveness, one sample point is at approximately elevation 30' which is below the operating deck, the other at elevation 90' above the operating deck. %is is consistent with the monitor's other safety functions. %e representativeness of duct sample points when compared to the moving air stream being measured mnsidered the size and shape of the duct as described in ANSI N13.1, Appendix A. Ebr example, the plant vent stack nonitor (2/3 RT-7808) has twenty sampling nozzles. Similar nozzle design considerations were made for the other monitors that sample from duct or air streams and are listed on Table 1. Isokinetic sampling refers to withdrawing a smple frm a flowing stream at the same velocity as the flowing stream. W is ensures that no prefer-ential sampling of different particle sizes will be made. Only the following nonitors are designed for isokinetic sampling. a) Plant vent stack Monitor (2/3 RT-7808) b) Radwaste disposal area vent (2/3 RT-7809) c) Fuel handling area vent (RT-7822-1, RT-7823-2) d) Control rom airborne (2/3 RT-7824-1) e) Condensor air ejector wide range monitor (RE-7870-1) f) Containment purge and plant vent stack monitor (RE-7865-1) . a,.~._

NRC Item 2 ne smpling point for isokinetic samplirs, following the guidance of ANSI N13.1 should nominally be five diameters (or equivalent) downstream from abrupt changes in flow direction or prominent transitions. khere five diameters cannot be met the sai.ple point is placed as far downstream frm abrupt changes as practicably consistent with maintaining reasonable ~ sample lernth. %is guidance was followed for all monitors designed for isokinetic sapling. %e condensor air ejector gas monitor (RT-7818) was designed to this five diameter criteria, even thouah it has no requirement for particulate sampling. In order to maintain isokinetic sampling on the NMC monitors the sample line flow rate is adjusted manually to match the velocity. For the plant vent stack monitor (2/3 RP-7808), there is turbulent flow in the duct, making the velocity distribution across the duct nearly uniform at the nozzle. Werefore, the flow rates in all the nozzles are the same. %e ratio of the_grosssection of the nozzles to the crosssection of the duct is 3.58 x 10. Figure 1 plots plant vent st ack flow rate versus isokinetic sampling rate. From this figure it can be seen for the existing plant configuration of approximately 60,000 cfm Unit 2 stack flow and 63,000 cfm Unit 3 stack flow the plant vent stack airborne monitor is at approximately 4.5 cfm to maintain isokinetic sampling. We wide rance gas monitors have a flow control valve which autmatically adjusts the sample flow to maintain isokinetic sampling over a range of duct flow rates. 1or example, wide range gas monitor (RE-7865-1) varies the sample flow frm 1.1 to 1.7 cfm in response to plant vent stack flow of 57,300 to 85,900 cfm to maintain isokinetics. %e plant vent stack monitor (and similar NMC mnitors) and wide range cas monitors have low and high sample flow alarms which will inidicate when the sample flow rate deviates from the established value. Wis provides a direct indication of an isokinetic flow. When an isokinetic suple condition occurrs., the correction factors of ANSI N13.1 Appendix C can be applied. %ese correction factors show that for a 10% change in duct flow assuming the sa pling flow rate is not adjusted accordingly, an error of 1% would result in the sample for a typical particulate size of 4p. An effort was made in the San Onofre 2 & 3 design to minimize the number of sample line bends and length to reduce particle deposition. As was discussed earlier, cmpromises between the best location for sampling and other factors were made. An analytical evaluation of the plateout in the plant vent stack lines has been made following the guidance of ANSI N13.1 Appendix B. %is evaluation took into consideration gravity deposition, brownian diffusion, turbulent deposition and deposition in elbows. Similar evaluations for other sample lines are currently in progress. An independant calculation of line losses for the plant vent stack m nitor is planned. % is will provide further confidence in the accuracy of the conservative line loss values being assumed.

~ NRC Item 2 W e calculated values will be used on an interum basis as a conservative correction factor for potential releases during early plant operation. Arrangements have been made to perform actual radionuclide measurements at the sa ple probe and detector locations to provide actual line loss factors under plant operating mnditions. % is testing will occur as soon as statistically significant releases are occurring, estimated to be at approximately the 50% power level. Eb11owing testing, these actual correction factors will be incorporated in station procedures. If condensation occurs in the sample lines, water may enter the monitor causing the detector to fail, or providing wetted surfaces to which the material of interest may adhere. If a detector fails (due to moisture or other causes), the operator is alertad to a channel failure. To avoid misture condensation problems, the following mnitor sample lines have been heat traced: 1) Containment and plant vent stack wide rarge monitor, switchable (RE-7865-1) 2) Condensor air ejector wide range monitor (RE-7870-1) 3) Condensor air ejector gas monitor (RT'7818) (prior to monitor operability) 4) Containment airborne mnitors (RT-7804-1, RT-7807-2) (Heat tracing to be installed prior to first refueling when condensation may be expected). In the design of heat tracing for sample lines, heat sinks at pipe support and wall penetrations are considered (Unit One problem). Insulated tubing clamps and/or additional heat tracing is used to reduce the temperature drop to acceptable levels at potential heat sink locations. The waste gas header, fuel handling vent, control room airborne mnitors and their associated s mple lines are located entirely within buildings. Ebr these lines no moisture condensation is expected to occur. 1 l We plant vent stack airborne mnitor (RP-7808) sample lines will be covered with one and a half inches of insulation. % is will maintain the qas sample above the dewpoint (no condensation in the line) assuming severe atmspheric conditions (e.g. low outside temperature and 100% relative t humidity) and 10,000 cfm of saturated air due to a postulated steam line break. Ilowever, as was discussed in a previous iten on the enhancement of the plant vent stack airborne monitor, these sample lines will be rerouted to provide additional system capabilities and, as part of this modification, will be heat traced. % e radwaste disposal area vent i (RT-7809) has a short distance exposed to outside atmspheric conditions. % is portion of the line will be insulated. >$*tW MSMW -Sf' ' %'aWY O'

'IABLE 1 NUMBER OF MONI'IOR SAMPLE N0ZZLES DUCP SIZE REFERENCE 2 Plant Vent Stack Airborne 20 64" x 70" = 31 ft S023-606-1-84 (2/3 RT-7808) 2 Radwaste Disposal Area Vent 20 80" x 68" = 38 ft S023-606-1-84 (2/3 RP-7809) Puel Handlina Bldo. Airborne 5 44" duct I.D. S023-606-1-34 (RT-7822-1, RT-7823-2) 2 Control Room Airborne 9 76" x 34" = 18 ft S023-606-1-84 (RT-7824-1, RT-7825-2) Condensor Air Ejector Gas ~ 2 14" duct I.D. S023-606-1-86 (RT-7818) (See Note 1) Condensor Air Ejector Wide Range Monitor (RE-7870-1) 3 14" duct I.D. S023-606-4-21 2 Ctmt. Purge and Plant Vent Plant Stack: 13 8'4" x 35.5" = 24 ft S023-606-4-15 2 Stack Wide Range Monitor Purge Stack: 11 4'2" x 35.5" - 12 ft S023-606-4-15 (Switchabe) NOTE 1: 'Ihe number of smple nozzle points is one less than the minimum recmmended number in ANSI N13.1. This monitor is gaseous detector only and smple nozzles are arranged to get representative gas flow, hDPE 2: Waste Gas Header Monitor and Containment Airborne Monitor do not s m ple a l duct air stream. l l t

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, Enclosure 2 NRC Iten 5 Radiation Monitoring System Data Review An independent review of work on the last four nonitors (Radwaste Discharge Line, Stet.n Generator Blowdown Neutralization Sunp, Turbine Plant Sump and Hi-Range in Contairinent Radiation Monitors) has been completed and data packaaes assembled. %is review has again confirmed that: I. Vendor calibrations were acceptably performed in accordance with procedures, II. Field work was performed acceptably and all repairs /modifica-tions which could have invalidated results were suitably retested and, III. % e sources utilized in the field are relatable to the vendor calibration by virtue of the vendor certification of the comparison of the field source to an NBS traceable source of the same isotope and geanetry and similar source strength. Data packaces for the remaining four monitors have been assembled and are available for inspection at the site. For each monitor these packages contain the following information: (1) Vendor Calibration Data (2) Vendor Calibration Procedures (3) Startup Calibration Data (4) Startup Calibration Procedures (5) Calibration and Standardization source certificates - NBS Traceability (6) Maintenance Records of each monitor.

NRC Item 5 (continued) We remaining priority II monitors will not be declared operable utilizing startup data, but rather will be brought on-line in the upgrade program at a later date. Justification for this is contained in the Technical Specifi-cation revision and may be sumarized as follows: 1) SJAE Monitor - Not required until Initial Criticality per Table 4.3-9 (# footnote) 2) Waste Gas Header Monitor - Plant Vent Stack Monitor (RE-7808) also serves as the waste gas header monitor (Table 4.3-9). Wis mnitor (RE-7808) will be declared operable utilizing Startup data. % erefore, the waste gas header mnitor (RE-7814) ~ may be held out of service in order to perform the uparaded calibrations, sv

NRC Ito.i 7: ODCM Manual ti The ODC/ Manual and its implementing procedures have been updated in response to NRC comments. This update included addition of calibration curves in the ODCM. The ODCM manual is being transmitted to NRR and should e received on Friday 2-5-82. The ODCM implementing procedures are in final review for approval and will be approved and issued by j Monday 2-8-82. 1 i I t k I I l l t I l - e ee-o.o m e m a ' a.nem

NRC Item 8: TRAINING To provide for appropriate training on the Effluent and Process Radiation monitors required for Plant Mode 6, the following actions will be completed: l. A syllabus and fact sheet will be given to appropriate Health Physics Technicians, Instrument and Control Technicians and Operators for study. A test will then be administered and graded to demonstrate familiarty with the monitors. This will be completed for sufficient personnel to cover all shifts by February 8,1982. 2. Orientation Training in a classroom format will be provided to personnel to supplement Item 1 above on February 8,1982 and will be repeated until all personnel have attended. 3. As the program documents'are completed (Procedures, Instructions etc.) they are placed on the' required reading program and signatures on the " Acknowledgment of Information" forms are required to provide objective evidence of this training. The schedule for procedure issuance was attached as Enclosure 6 to the February 1,1982 letter. l l

NRC Iten 10: QUALITY ASSURANCE PROGRAM CONSIDERATIONS F'OR REGULATORY GUIDE 4.15 REVISION 1 COMPLIANCE PROGRAM BASIS Code of Federal Regulations;_10CFR50 Appendix B Criterion. I. Organization II. Quality Assurance Program IV. Procurement Document Control V. Instructions, Procedures, and Drawings VI. Document Control VII. Control of Purchased Material, Equipment and Services IX. Control of Special Processes XII. Control of Measuring and Test Equipment XIII. Handling, Storage and Shipping XVI. Corrective Action XVII. Quality Assurance Records XVIII. Audits Topical Quality Assurance Manual (TOAM) Chapter 8-B covering; 1.0 Introduction 2.0 Organization and Responsibilities 3.0 Qualification and Training of Personnel 4.0 Operating Procedures and Instructions 5.0 Records 6.0 Procurement Control 7.0 Sampling, Packaging, Shipping and Storage 8.0 Calibration and Control of Measuring and Test Equipment 9.0 Review Analysis and Reporting of lata 10.0 surveillance and Audits DRAFT QUALITY ASSURANCE PROGRAM CONS: ERATIONS (NARRATIVE STATEMENTS) Regulatory Guide 4.15 Revision 1 entitled; Quality Assurance for Radiological Monitoring Programs (Normal Operations) - Effluent Streams And The Enviornment is very specific in the needs for a Quality Assur-ance program. This Quality Assurance program, is to be implemented by various organizations within the company. The Regulatory Guide requires that Health Physics, Chemistry, Operations and the Instrumentation and Control organizations apply certain Quality Assurance program elements to their activities. Quoting from Regulatory Guide 4.15, " quality assur-ance comprises all of those planned and systematic actions that are a

necessary to provide adequate confidence in the results of the monitoring program and quality control comprises those quality assurance actions that provides a means to control and measure the characteristics of measurement equipment nd processes to establish requirements; "therefore, quality assurance includes quality control.'" The reasons for the regulatory guide is to assure not only the Nuclear Regulatory Commission but also the general public that the results of our radiological monitoring programs are reasonably valid and that the general public will have a high degree of con-fidence in the results we report. The ipecific requirements that must be implemented to comply with Regulatory Guide 4.15 Revision 1 are; 1) organizations participating in the Quality Assurance program and performing measurement activities shall be able to identify deficiencies in the sampling and measurement processes and provide for corrective action.

2) To document the shipment of samples, the receipt of samples in the laboratory for analysis, the preparation of samples, the measurement of radioactivity, the reduction of data, evaluation of the data, and the reporting of monitoring results.

These QA program elements are applicable to the licensee or the licensee's contractors. Also QA program rou-tine data summaries to evaluate the effectiveness of the program shall be provided. ORGANIZATION, STRUCTURE AND RESPONSIBILITIES OF MANAGERIAL AND OPERATIONAL PERSONNEL As it relates to the management and operation of monitoring pro-grams, the organizational structure and responsibilities shall be defined including the authorities, duties, and responsibilities down to first line supervisory personnel. The personnel respon-sible for the evaluation, review, and approval of monitoring data and reports shall also be defined. SPECIFICATION OF QUALIFICATIONS OF PERSONNEL Qualifications of individuals performing radiological monitoring shall be documented in a job description. An indoctrination and orientation program for these personnel shall be provided to assure that they are familiar with the principles and techniques of the activities they will be performing. Additionally the personnel must be aware of the nature and goals of our Quality Assurance program. The proficiency of these personnel shall be maintained by retraining, reexamining, and recertifying or by periodic per-formance reviews. -- -~ u-m

-e-sample is representative of material volumns sampled. Grab sampling procedures shall include; l) steps to insure a representative sample is obtained, and 2) replicated grab samples shall be taken periodic-ally to determine reproducability. QUALITY CONTROL IN THE RADIOANALYTICAL LABORATORY Reference standards used to determine counting efficiencies for speci-fic radionuclides shall be used. Gamma-ray-spectrometry efficiencies as a function of gamma-ray energy shall be determined. Standards certified by the National Bureau of Standards (NBS) or suppliers who participate in the Measurement Assurance ?rogram (MAP) shall be used. PERFORMANCE CHECKS OF RADIATION MEASUREMENT SYSTEMS Determination of background and the response of each detector shall be made on a scheduled basis. Thouc results shall be logged and plot-ted on a control chart. Investigation and corrective action shall be taken when measurement values fall outside of predetermined control values. ANALYSIS OF QUALITY CONTROL SAMPLES Quality control samples to determine the precision and accuracy of mon-itoring processes shall include; 1) interlaboratory, 2) intralaboratory,

3) analysis of replicated samples for the determination of precision,
4) analysis of known concentrations to provide for the determination of accuracy.

INTPJ. LABORATORY ANALYSIS Replicate samples are usually duplicates of monitoring samples. Anal-ysis of replicate samples is desirable but is not always practicle for all samples in all labs. Replicate samples of airborne material is usually not practical on a routine basis. Spiked and blank samples however are an important element in a Quality Control program. It is important to include these spiked and blank samples within known and unknown samples sent to laboratories for verification. This type of a program will develop a high degree of confidence in the laboratories performing measurements for SCE. INTERLABORATORY ANALYSIS Effluent and environmental samples split with one or more independent laboratories is also an important element of the Quality Control pro-gram. This allows some means of detecting errors not detectable by using one laboratory. All laboratories utilized by SCE should have traceability to NBS. These split samples are an important part of the environmental monitoring program due to the low level of concentrations in environmental samples. ..-~.--w

- + COMPUTATIONAL CHECKS Independent verification should be performed on a substantial frac-tion of the test results obtained. Computer input data should be verified by knowledgeable individuals. QUALITY CONTROL FOR CONTINUOUS EFFLUENT MONITORING SYSTEMS The specified calibration frequency shall be based on the nature and stability of the system. For the SONGS 2&3 systems the' frequencies are defined within the Technical Specifications. Initial calibrations of these systems should be made with reference standards traceable to NBS or with standards supplied from suppliers who participate in the MAP program. These systems shall be calibrated for their intended range of energy and rates. Also initial calibration sources should be used for calibrations performed at each refueling interval or ap-proximately 18 months. Grab samples shall be used to periodically check system performance. Any systems with flow rate measurement devices should be calibrated initially and these devices shall be re-calibrated periodically. REVIEW AND ANALYSIS OF DATA Procedures for review and analysis of data must be provided to assure that reccrds are consistent and reasonable. These procedures should also require that the data is reviewed and analyzed in a timely manner. The procedures must specify the acceptance criteria and also the method for the correction of document deficiencies. AUDITS Planned and periodic audits to verify implementation of the monitoring program shall be performed by Quality Assurance. These audits shall be performed by individuals qualified and knowledgeable in the radio-chemistry and monitoring techniques utilized. Audit results will be discussed with management in the area audited. Also followup of any corrective actions including reauditing of those activities shall be performed. IMPLEMENTATION Regulatory Guide 4.15 Revision 1 will be used after March 30, 1979 except in those cases in which the applicant or the licensee proposes an acceptable alternative method. l l l ea.i s

OPERATING PROCEDURES AND INSTRUCTIONS i Written procedures for the monitoring program shall be provided. These procedures shall cover; sampling collection, packaging, shipment, re-ceipt of samples for offsite analysis, preparation and analysis of sam-ples, maintenance, storage, use of radioactivity reference standards, calibration, checks of radiation and radioactivity measurement sys-tems, the reduction, evaluation and reporting of data. Individuals who review and approve these procedures should be knowledgeable in the subjects of the procedures reviewed. RECORDS Records necessary to document these Quality Control activities shall be specified. These records shall include field collection, inplent collection for analysis including sample description, sample receipt, and laboratory identification coding, sample preparation, radio chemi-cal processing, e.g. lab note books, radioactivity measurement of samples, instrument background measurements, analytical blanks, data reduction, and verification records. Quality Control records shall also be maintained for the results of measurement of radioactivity check sources, calibration sources, backgrounds and blanks, and re-cords relating to overall lab performance. In addition, records shall be maintained for any standards developed by SCE labs such as the preparation and standardization of carrier solutions and cali-bration of analytical balances. ADDITIONAL RECORDS REQUIRED ' Additional records required to be maintained are calibration of inline radiation detection equipment, blank samples, thermoliminescence dos-imetry systems, verification and documentation of. computer programs 1 and the qualification of personnel. i RECORD RETENTION l Records shall be maintained in accordance with Station and CDM pro-cedures. QUALITY CONTROL IN SAMPLING (INCLUDING PACKAGING, SHIPPING, & STORAGE OF SAMPLES; Continuous sampling of liquid and gas flow rates and/or sample volumns t must be verified. The accuracy of these devices should be determined on a regularly scheduled basis. The calibration results shall be documen-ted. The frequency of the calibrations shall be based on 1) required accuracy of the system, 2) purpose of the system, 3)~ degrees of usage and 4) stability characteristics and other conditions affecting measure-ment. Procedures for continuous sampling methods should insure the .--h- ~. m e * - 3'1. A Str Me * @ #

ATTACHMENT 2 (REVISION 1) - e v REGULATORY GUIDE 4.15, REVISION 1 PHASED APPROACH 9 Fuel 10CFR50 Appendix Load Station Procedures' B Criteria 2/82 3 4 5 6 7 8 9 10 11 12 1/83 2 3 4 Affected 4 I Organization P I A C Q-1 II QA Program P I T A C Q-2 III Design Control N A IV Procurement - P I - A C Q-4 Document Control V Instructions, Pro-P I A C Q-5 cedures, Drawings VI Document Control P I A C Q-6 VII Control of Pur. - P I - A C Q-7 Mat. & Services VIII I.D. & Control N A i of Mat. Parts & Components IX Control of Special N A Processes X Inspection N A XI Test Control N A XII Control of Meas. P I A C Q-12 & Test Equipment XIII Handling, P I A C Q-13 Storage, & Shipping r XIV Insp. Test & N A Opn. Status XV Nonconforming Mat. N A Parts & Components XVI Corrective Action P I A C Q-16 { XVII QA Records P I A C Q-17 XVIII Audits P I T A C Q-18 P = PROCEDURE ISSUANCE T = TRAINING C = COMPLETE i I = IMPLEMENTATION A = AUDIT NA = NOT APPLICABLE * ' I i

  • (Other existing administrative controls are sufficient. )

Prepared by: j // 2/3/g;L Approved by: [ c~. 2[J[S t_ m / f I W f t

. [h 33stonifD 0R1030 Qg R?CEIVED C t Certified By__ y Southern California Edison Company lggg (gg l9 g; g,qT~ P o. BCX 8 00 2 2 44 W ALN U7 GMOVE AVENU E RO$ E M E AD C ALIFORNI A 91770 f, g, p, g A g a' I N TELENONE February 9,1982 .~... o,aue u. .~o.~e ..~. m n umn S.,E T w..N O E sC t hlaN G Director, Of fice of Nuclear Reactor Regulation Attenticn: Mr. Frank Mi raglia, Branch Chief Licensing Branch No. 3 U. S. Nuclear Rigulatory Commission Washington, D.C. 20555 Gentlemen:

Subject:

Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3 Reference is nade to my letter to you dated February 3,1982 concerning the implementation program for radiation mcnitors for San Onofre Nuclear Generating St ation, Units 2 and 3. Subsequently, NRC Region V personnel requested that a diff erent approach be utilized to provide schedule relief requested to allow sufficient time for enhanced calibration of radiation monitors. The new approach will incorporate a condition to the SONGS 2 and 3 Operating License that identifies in an appendix, the Technical Specification relief requested for radiation monitors. Pursuant to the Region V suggestion, a meeting was held on February 8,1982 at the Region V offices to reach agreement on the new approach. In accordance with agreements reached in that meeting, enclosed for your use are seven (7) copies (NRC Mail Code 6028) of the following material: : Tabular presentation summarizing the Technical Specification Relief requested. : Specific Technical Specifications, corrected to reflect the change in approach for requesting schedule relief. is considered suitable for appending to the SONGS 2 and 3 Operati'g License and referencing in a license condition that states: "Radiatior Monitors shall be provided consistent with Technical Specification (Appendix A) requirements, except as noted in Appendix If you have any questions concerning these matters, please call me. nk f Very truiy yours, i y suar 6 g - [." b b Enclosures cc: F. J. Wenslawski - Reaion V [

k s ENCLOSilRE 1 Technical Specification Relief l l l _._s......

Erclosure 1 '%. Radi'ation Monitors Monitor Technical Specification Relief Control Room Airborne

1) Calibrations performed during the startup pro-Monitors RT-7824/7825 gram in accordance with FSAR Section 11.5.2.1.5.2 are acceptable in place of the CHANNEL CALIBRATION requirements of the applicable Technical Specification section prior to initial pcwer increase above 5% Rated Thermal Power.

Containment Purge Area Monitors RT-7856/7857 Containment Area Radiatien-High Range RE-7820-1/7820-2 Radwaste Discharge

1) Calibrations perferned during the startup Line Monitor RT-7813 program in accordance with FSAR section 11.5.2.1.5.2 are acceptable in place of the Blowdown Neutralization CHANNEL CALIBRATION requirements of the Sump fionitor RT-7817 applicable Technical Specification section prior to initial power increase above 5%

Rated Thermal Power. Turbine Building 2) Testing performed in accordance with FSAR Sump Monitor RT-7821 Section 14.2.12 is acceptable in place of the initial CHANNEL FUNCTIONAL TEST requirements of the applicable Technical Specifications. Subsequent CHANNEL FUNCTIONAL TESTS are not required until 30 days after Initial Criticality. Steam Jet Air

1) Monitoring of the condenser evacuation path Ejector Monitor is not required until Initial Criticality.

RT-7818 A8B Plant Vent Stack

1) Calibrations performed during the startup program Airborne Monitor in accordance with FSAR Section 11.5.2.1.5.2 RT-7808 are acceptable in place of the CHANNEL CALIBRATION requirements of the applicable Technical Specification section prior to initial power increase above 5% Rated Thermal Power.

2) Prior to 5% Rated Thermal Power operation in Action Statement 19 (Table 3.3-6) shall be allcwed for up to 14 days for the purpose of performing the " initial CHANNEL CALIBRATION". Containment Airborne 1) Calibrations performed during the startup program Monitors RT-7804/7807 in accordance with FSAR Section 11.5.2.1.5.2 are acceptable in place of the CHANNEL CALIBRATION requirements of the applicable Technical Specification section prior to initial pcwer increase above 5% _ ma, + (Cont.)- Monitor Technical Specification Relief s

2) Either of these monitors and its associated particulate and iodine samplers is acceptable for containment purge effluent monitoring until Initial Criticality.

. Main Steam Line -Area Monitor RT-7874A1, RT-7874B1 RT-7875A1, RT-7875B1 Condenser Evacuation To be operational prior to initial pcwer System Radiation increase above 5% Rated Thermal Power. Monitor - Wide Range RT-7870-1 Purge / Vent Stack Radiation Monitor - Wide Range 2RT-7865-1, 3RT-7865-1 Waste Gas Header Plant Vent Stack Ponitor RT 7808 perforns Monitor 2RT 7814 the same functions as 2RT 7814 (monitors release and terminates on alarm). RT 7808 will be used in place of 2RT 7814 when 2RT 7814 is not operable. Sanpling Condenser Evacuation System Iodine Sampler Particul ate Sanpler To be operational prior to initial power Flow Rate Monitor increase above 5% Rated Thermal Power. Plant Vent Stack Flow Rate Monitor Containment Purge Flow Rate Monitor t i A Ouality Assurance Program for effluent and environmental monitoring (Technical Specification 6.8.1.i) using the guidance of Regulatory Guide 4.15, Rev.1, February 1979, shall be implemented prior to July 1,1982 or initial power i crease l above 5% Rated Thermal Power, whichever occurs first. Continuous proportional sampling (Technical Specification Table 4.11-1 TABLE NOTATION "C") provisions shall be operational prior to 1-1-83. In the interim, administrative controls shall provide for composite sampling of continuous releases per Technical Specification Table 4.11-1 TABLE NOTATION"b". l l l.

' (Cont.). y t lB. Additional Technical _ Specification Changes -Tech. Spec. Technical Specification Relief 1) 3/4 12.2 Requirements of these specifications shall not be-applicable prior to initial power increase above 5% -2) 3/4 12.3 Rated Therral Power in order to be consistent with the phased -implementation of Regulatory Guide 4.15, 3) 6.8.4.b. Rev.1, February 1979. 4) 6.8.4.d Requirenents of this specification shall not be applicable prior to initial power increase above 5% Rated Thermal-power.in order to be consistent with the operability schedule for the Post Accident Sampling Sy st en. { f i i h 4 'f 4. -~

s ( ENCLOSURE 2 Technical Specification Changes { vg n d, y /6M FN*a - Am W.4 , g g,

T 's [] Q-[ ~ s e t j. TABLE 4.3.-2(Continued), x i 3 4, ENGINEERED SAFETY EEATURE ACTUATION SY'.T_EM INS.TRifM.ENTATION SURVEILLANCE REQUIREMENTS CilANNEL H0 DES FOR Wil!CH E: CilANNEL CilANNEL FUNCTIONAL SURVEILLANCE TUNCTIONAL UNIT CllECK _C A_L__I_B R A T ION. TEST IS REQUIRID y 7. LOSS Of POWER (t0V) a. 4.16 kv Emergency Bus Undervoltage (Loss of Voltage and Dc0raded Voltage) S R R 1, 2, 3, 4 8. EMERGENCY FEEDWATER (EFAS) a. Manual (Trip Buttons) N.A. N.A. .R 1, 2, 3 b. SG Level (A/D)-Low and AP (A/B) - liigh S R H 1, 2, 3 c. SG Level (A/8) - Low and No d Pressure - Low Trip (A/B) S R H 1, 2, 3 d. Automatic Actuation Logic H.A. H.A. H(1)(3),SA(4) 1, 2, 3 9. Control Room Isolation (CRIS) a. Manual CRIS (Trip Buttons) N.A. N.A. R N.A. m L b. Hanual SIAS (Trip Buttons) N.A. N.A. R N.A. N.- c. Airborne Radiation i. Particulate / Iodine S R H All 1i. Gascous S it H All d. Automatic Actuation Logic n.A. fl. A. R(3)' All c:3 ca, ~ 10. Toxic Gas

  • Isolation (TGIS) a.

Manual (Trip Buttons) N.A. N.A. R N.A. U b. Chlorine - liigh 5 R H All l *T3 r c. ' Ammonia - liigh 5 R H All j !.M d. Butane / Propane - High 5 R M All F!A e. Carbon Dioxide - liigh 5 R H All ~ A'~- , ".',3 f. Automatir./shtuation Logic ti. A. N.A. R (3) M1 f g =3 'n l -c-1 f l

v "3 on0m*j7~.*C v jl a., p' i' r 2 5C {c f. hc 3 a n e o i f i t o l a CE I CD A. A. l ll l i n l l l l S t o I i E r S MAu N H AAA GA I i i T tl S n t N Rtu A a i r Oiq D r M F ti h i r yR T s c g R SR S l a r l EU5 E e e e u DS1 T n n q O n f e f M D a o e-R E h R c n d E E o / C G t i n N G n t o L ) A e a i l ) 3 T m z t. ay t L 3 ))) ( S u i ( 272 r g 7 a l LAl R HHR R ((( HR a t r il E Er V NoT s e ge R NI S n n n rr l i AT E o i e enp S ti CT CN s e ey eu u y s da o ir O r a e /l er I d h ne h g T t or tb A 2 i u 6 r t n es ) T l_ d o ao d 4 r A. r A ))) A y f zi uh A. e [ 0_ r i t l c 272 u M L 1_ n li ET RRN. N ((( Rl N e s ga ca l f f i P I A-O v t ri nc F t T R I e n et i F n 5 AO T e ni f n.,,(C-e i T A t m en l o 4 t I CI. T s e i l M C_ l a r e aY A_ 0 e i dh h! f 7 F l u oc sI S T, F q l a L A 3 S L t e ce hI I lg Y B a r n cB C A i f iA 4 S A. T d e o hR n p A A. A ))) E N L 2?2 wL e c l i t O EK N S5f l. l l f ((( Sf .t n l Y i e D I NC s a al dO t m A T NE e i hI e iMo T AU iC t l sL me AI r l I l l rh T C e e c0 ot t i C .b v iA f r s A ) r gR rf S l u oE eo.t s E I l s LP 'p o d R P n a O n n U ) c C o c h 9 n eo T S i ( i i s oe bi s A l g t g 3 ih t e l, E i eo n a o l tt l a o l F F) nL o) i L e c a l c d t ( s i is d n uf ai r Y n d n t n a n n e t o hf T non oo aon R o a l c si y o h b An r l f E ot o Ii l t o i F i ti /t oti e a t c a o te n A t ut ea sut t e a T ci sv o A S aBa t u IBa a r u c i t e n h t a td t at i l A t i l i D opd l c epd su c g t ac n n t. E siasuA gi a u c e t A o i mi ya e i R I rRuc rrR oinn l w of a m E T oic uT eti e c ti l y p d E g( eeti P( esrdm i r e ur ea i a N n nsrt naaon)t o c Ae rl u r I il raaa tl rGPIi aa n v e q r G T l aoGP m nao awm n a f pr e . t n o i d od u T. 4 I d ub o eub t E N nnr .t mnr .inat a r n op d U aai .iu nai.iioGu r o ga ru e l l AiiA iMAiiiC(A t c n go t l f y br a L a c i A l t h a ta ug u l N e n c sl sb t V O u o.. a n ee u c m.. I Fab c Cab c d E I Tr As A T C N ) ) ) ) ) 4 U 1 2 1 2 3 4 5 F 1 1 ( ( ( ( ( p h A /mw* " w) wJw l l 'i.l il1:!*;; ;i-j !J f jt ; 1 t iI tlf(lIii

R r TABLE 3.3-6 y Z RADI ATION MONITORING _ A' ARM INSTRUMENTATION E ? A MINIMUM J. CilANNELS APPLICABLE ALARM-MEASUREMENT ,. 5 INSTRUMENT OPERABLE MO D E S...-. SETPOINT RANGE ACTION ,1. Area Monitors a. Containment.- High 2 1, 2. 3 R/hr 1-10" R/hr 18 Range 4 g R/hr 19 b. Containment - Purge 1 1,2.3,4 < 325 mR/hr 10 1-105 mR/hr 19 Isolation 6 Il (a) c. Main Steam Line 1/line 1, 7, 3 1 mR/hr (lowl-10 8-10* mR/hr; 18 I R/hr (high) R 4 1 mR/hr (low); 19 1 R/hr (high) y ty, 2. Process Monitors a. Fuel Storage Pool Airborne i. Gaseous 'l 101 -10 cpm (d) 7 ii. Particulate /Iodir.e 1 108 -10. cpm (d) 7 b. Containment Airborne ii. Particulate .1 All Per ODCM 108 -107 i. Gaseous 1 All Per ODCM 108 -107 com (a)(b)(c) cpm (a)(b)(c) s iii. Iodine 1 All Por ODCM 108 -107 cpm (a)(c) c. Cont ol Room Airborne 1. Particulate / Iodine 1 All 101 -107 cpm (c) ii. Gas'ous l' All 101 -107 cpm (c) c L p' i t L

A ^ TABLE 3.3-6 (Continued) s = g 4 8 RADIATION MONITORING ALARM INSTRUMENTATION 1 ? 5 c'- MINIMUM E CHANNELS APPLICABLE ALARM MEASUREMENT . _C T I_O_N INSTRUMENT OPERABLE MODES _ 5ETP0lNT RANGE A m 3. Noble Gas Monitors c a. Plant Vent Stack 1 All Por 00CM 108 - 107 cpm 19 (c) 3 i b. Condenser Evacuation 1 .0 e System 1 All Por ODCM 108 - 10 cpm 19.(c) 7 c 4 e t ? l i w , n'l N s i

  • I w

k a m ).* 4 <:..s ' I. Il. i 3 i:

,s i

i '. i ; l~ t ' r <j f (. t !.

.v t... Ar l!C:. 51/.11it NIS (; P ACTION 18 - With the number of channels OPERABLE less than required by the Minirium Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.3.3.6. ~ With the number of OPERABLE Channels less than'the Minirtum C110N 19 - Channels OPERABLE requirement, restore the inoperable Channel (s) to OPERABLE status within 7 days, or be in at least HDT STANDBY within the next 6 hours, and in at least HOT SHUTDOWN within the following 6 hours and in COLD SHU1DOWN within the subsequent 24 hours.

  1. 1n accordance with Engineered Sa. ty Feature trip value specified by Table 3.3-4.

With irradiated fuel in the storage pool. (a)ln accordance with Tab'.- 3. 3 ACT ION 17. (b)ln accordance with Table 3.3 ACTION 17a. (c)ln accordance with Table 3.3 ACTION 171,. (d)ir,iu.ordance with Tabie 3. ' AC i l0N 16. (e)ir e c e..b 'ic c w i t h 41 i t. 3. ? 6: : !C% 13. SAN ON0fRE-UNIT 2 3/4 3-37 .. --...:. ~ ~ .:... : :- - =r : - :.- ' .~ .= . - s n a.,- w._a

n m I: TABLE 4.3-3 \\ 6 F s RADIATION MONITORING INSTRUYENTATION SURVEILLANCE REQUE EMENTS a; 7 CHANNEL MODES FOR WHICH E CHANNEL CllANNEL ruNCT10NAL SURVEILLANCE } INSTRUMENT CHECK CALlBRATION TEST IS REQUIRED m 1. Area Monitors a. Containment - High Range 5 R H 1, 2, 3, 4 b. Containment - Purge Isolation S R H 1, 2, 3, 4 G c. Main Steam Line 5 R H 1,2,3,4 2. Process Monitors a. Fuel Storage Pool Airborne ,1 i. Gaseous i i.. Particulate / Iodine w b* m b. Containment Airborne i. Gaseous 0 All k *,9 ii. Particulate 0 0 All 8 iii.- Iodine 0 0 All j a f c. Control Room Airborne 8 i. Particulate All 11. Gaseous All 9 i.; l. i d-

A p.m s E TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 5 CHANNEL MODES FOR WHICH E CHANNEL. CHANNEL FUNCTIONAL SURVEILLANCE y INSTRUMENT CHECK CAL _IBRATION TEST IS REQUIRE 0 PROCESS MONITORS (Continued) 3. Noble Gas Monitors a. Plant Vent Stack 0 All Ij, b. Condenser Evacuation System O All R = .i Y NOTES: W 9s y 4 ~ In accordance with Table 4.3-2 surveillance requirements for these instrument channels, t I 3.. ' Jj ' With irradiated fuel in the storage pool. 3 t i.t g ?' In accordance with Table 4.3-9 surveillance requiromonts for these instrument channels. 1

4 fi i$

, {! I L

..? y TABLE 3.3-10 i = ACCIDENT MONITORING INSTRUMENTATION (CONTINUED) e Aa RE00lRED MIN!!10fl NUMBER Of CHANNELS ~* INSTRUMENT CHANNELS OPERA 0LE to 19. Containment Area Radiation - High Rango 2 1 20. Main Steam Line Area Radiation 1/ steam lina N.A. 21. Condenser Evacuation System Ra'diation Monitor - 1 N.A. Wide Range 22. Purge / Vent Stack Radiation Monitor - Wirin Hanon* 2 1 23. Cold Leg HPSI Flow 2/ cold Icq 1/ cold lai R 24. Hot Leg HPSI Flow 1/ hot inq N.A. a Y I l .l NOTES:

  • The two required channels are the Unit 2 rnaitor and the Unit 3 monitor.

e i.!: it ? $' h 9 9 (

4 'A TABLE 4.3-7 = 3 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS (CONTINUED) a A E-CHANNEL CllANNEL { INSTRUMENT CIIECK CALIBRATION 19. Containment Area. Radiation - High Ranga (a) (a) 20. Main Steam Line Area Radiation (a) (a) i 21. Condenser Evacuation System Radiation Monitor - M R Wide Range 22. Purge / Vent Stack Radiation Monitor - Wide Ranoo M R 23. Cold Leg ilPSI Flow M R i-24 Hot Leg flPSI Flow M R R ~ ~ n 3-Y i.i -y-i NOTES:

i. ' t 1

. s. (a) In accordance with Table 4.3-3. I i' l.- t. i 's s

  • e l

\\, l 1.

  • M b

m I' r L

r 1 Pan n o B.,M COPY INSTRUMENTATION ra e Rt.DI0 ACTIVE LIQUID EFFLUENT MONITCRIN3 INSTR _U_M_ENTAT;s, LIMITINGCONDITIONF5ROPERATION 3.3.3.8 The radica:tive liquid effluent monitoring instrurentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are net exceeded. The alaru/ trip setpoints of'these channels shall be determined in accordance with the OFF5ITE DOSE CALCULATION M*NUAL (0DCM). APPLICABILITY: At all ticts ACTION: a. With a radica:tive licuid ef fluent monitoring instrumentation channel alarr/ trip setpoint lestr conservative than required by the above specification, inmediately suspend the release of radioactive liquid effluents mcnitored by the affe:ted channel or declare the channel ir.cperable. b. With los than tr.e minir.n. number of radi:6:the liquid ef fluent m: nite-in; instn intiticn channels OPEFJE'.E, ta!s the 'CTION sheva 7g ir. Tatie 3.3-12. c. ibt p :si::c. cf 5;e:ifications 3.0.3 a " 3.C.4 a e n:t a;plicatie. SURVEILLANCE REOUIREMENTS 4.3.3.8.1 Each radioactive liquid ef fluent monitoring instrumentation channel ~ shall be de onstrated CPERABLE by perforcance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIERATION and CHANNEL FUNCTIONAL TEST cperations at the frequencies shown in Table 4.3-8. 4.3.3.8.2 At least once per 4 hours at least one circulating water pump shall be deterni.ned to be operating and providing dilution to the discharge structure whenever dilution is required to meet the site radicactive effluent concentration limits of Specification 3.11.1.1. l i l l l ( l e SAN ONOFRE-UNIT 2 3/4 3-63 i 7 ( ....,.c.. ._,,_,,g

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C, . ~. n ~ * ~ e* "n r e'hJul u. !!. W yl. ;m.r TABLE 4.3-8 (Continued) i-n , L..es .o s " " ~ ~ - - TAELE NOTATION (1) The CHANNEL FUNCTIONAL TEST shall also dex.cnstrate that automatic isolation of this patNay and centrol recs alar:. annun:f ation occurs if any of the felicsing concitiens exists:* 1. Instrument indicates measured levels abcve the alarm / trip setpoint. 2. Circuit failure. 3. In:tra ent indicates a d:-nscale failure. (2) The initial CFAN'.EL CA;.IE:.ATICN shall te pert,r ed usir.; cne er trere of the reference standarcs u rtified by the Naticnal Bureau cf Standards or using standards that hase been obtained from suppliers that participate in reasurerent assurance activities with NES. These standards shall per.?.it calibrating the syster,ever its intended ran;e of e.ergy'and reasure ent ran;e. For st.bsequent CHANNEL CALI5:.ATICN, scurces that have been related to t'.e initial calibration shall be used. (3) CHANNEL CHECK shall censist of verifyir; indi:ation of flew during pericts of release. CHAMEL CHECK shall be r.ade at least on:e per 24 hours on days en which c:ntir.arvi, periedic. or tatch releares are medc. .r- \\.' TIf the instrc: ent centrols are not in the operate mcde, procedures shall call for declaring the channel incperable. ( SAN ONOFRE-UNIT 2 3/4 3-67 ~.. - - =0' swe

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i..... l9 ,? I t.!* l [ u.)1 A1 J 0'; At all times. During waste gas holdup system operation (treatment for primary system offgases). a) In accordance with Table 3.3-6 ACTION 19 b) In accordance with the ACTION Requirements of Specification 3.4.5.1 (Modes 1, 2, 3 and 4) c) In accordance with the Atl]DN Requirenent of Specif ic<tien 3.9.8 (Mode 6) ACTION 35 - With the number of channels OPERABLE less than required by the Minirum Channels OPERABLE requirement, the contents of the tank (s) may be released to the ensironment for up to 14 days provided that prior to initiating the release: a. At least two independent samples of the tank's contents are analyzed, and b. At least two technically qualified members of the facility Staf f indcpendently verify the release rate calculations and discharce valve lineup; ( Othcrwisr, suspend reitar.e of radioactive effluer,ts via this path.sy. ACl]ON 36 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provide'd the flow rate is qstimated at least once per 4 hours. ACTION 37 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requ.irement, effluent releases via this pathway may continue for up to 30 days provided grab sanples are taken at least once per 8 hours arid these samples are analyzed for gross activity within 24 hours. ACTION 3B - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, immediately suspend PURGING of radioactive effluents via this pathway. ACTION 39 - With the number of channnels OPERABLE one less than required by the Minimum Channels OPERABLE requirement. operation of this system may continue for up,to 14 days. With two channels inoperable, be in at least HOT STANDBY within 6 hours. ACTION 40 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via (7 the af fected pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11-2. l SAN ON0fRC-UNIT 2 3/4 3-70 l

_

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f*% O s TABLE 4.3-9 I, E RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INST 81UMENTATION SURVEILLANCE REQUIREMENTS e.. ? CHANNEL MODES FOR WHICil CilANNEL SOURCF CHANNEL FUNCTIONAL SURVEILLANCE E ~ ch INSTRUMENT CilECK CilECK CALIBRATION TEST IS REQUIRED b 1. WASTE GAS HOLDUP SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic Termination of eee R T-770 S P P R(3) Q(1) 2/3 RT .781 o s. Vi

b. Flow Rate Monitor,

P N.A. R Q 1 2. WASTE GAS HOLOUP SYSTEM EXPLOSIVE i' GAS MONITORING SYSTEM i.

a. Hydrogen Monitor (continuous)

D N.A. Q(4) M j ;. R.

b. Hydrogen Monitor (periodic)

D N.A. Q(4) M s

  • l
c. Oxygen Monitor (continuous)

D N.A. Q(5) M y i-5

d. Oxygen Monitor (periodic)

D N.A. Q(5) M l,- 3. CONDENSER EVACUATION SYSTEM }

a. Noble Gas Activity Monitor -

[I 2RT - 7818, 2RT - 7870-1 D M R(3) Q(2) ~~ i

b. Iodine.' Sampler W

N. A. - N.A. N.A. r I

c. Particulate Sampler W.

N.A. N.A. H.A. ? i

d. Flow Rate Monitor O

N.A. R Q l 4. PLANT VENT STACK i*

a. Noble Gas Activity Mon *to 3p W@l j,

2/3 RT - 7808,0 A, L RT.7 & 1 ^" M R(3) Q(2) l

b. Iodine Samp1 W

N.A. N.A. N.A. g. j

c. Particulate Sampler W

N.A. N.A. N.A.

d. Flow Rate Monitor'-

D N.A. R Q I

e. Sampler Flow R. ate Measuring i

Device D N.A. R Q t i.

3-C $R _ TABLE 4.3-9 (Continued) s E RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS z E% A CilANNEL MODES FOR MilCll CilANNEL SOURCE CilANNEL FUNCTIONAL SilRVEILLANCE INSTRUMENT CilECK CliECK CALIBRATION TEST IS REQUIRED w N 5. CONTAINMENT PURGE SYSTEM (.~7) 4

a. Noble Gas Activity Monitor -

Providing Alarm'and Automatic mination of R Ic 2 -* - RT - 7804-1 E - 7607 2" S P(6) .H(3) M(1)

b. Iodine Sampler.

'W ti. A. N.A. N.A.

c. Particulate Sampler W

N.A. N.A. N.A. 1

d. Flow Rate Monitor

.G N.A. R Q s

e. Sampler Flow Rate Measuring a

y Device D H.A. R .Q M i l 1 s t r I 4 g. I.~. s. 1 ? ( O

,7 Tffif. A. 3-Q ((en t v: ve J) e*'~ (i 1 Ai:, i !.*>T A1 J ON 8 At all times. During waste gas holdup system operation (treatment for primary system offgases). (1) The CHANNEL FUtCTIONAL TEST shall also demonstrate that automatic isclation of this path.eay and control r any of the follo ing ccnditions c>ists:pon alarm arinunciation occurs if 1 Instrar..ent indicates ressured levels above the alt m/ trip setpoint. 2. Circuit failure. 3. Instrument indicates a downscale failure. (2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control root alarm annunciation occurs if any of the following conditions exists": 1. Instrument indicates reasured levels above the alare setpoint. 2. Circuit failure. 3 I ns t re.c nt m ic:-t.i a d:., ;.cale f ailure. (3) lii. init ial CF.~.'.NLi cat i: RATICN st.all be perf c rred usirig v.e cr r ea e of the reference standards certified by the National Bareau of 5'andards or using standards that have been obtained from suppliers that p rticipate ir measurement assurance activities with NB5. These standards shall per....t calibrating the system over its intended range of energy and measurement range., For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used. (4) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal: 1. One volume percent hydrogen, balance nitrogen, and 2. Four volume percent hydrogen, balance nitrogen. (5) The CHANNEL CALIBRATION shall include the use of stands.rd gas samples containing a nominal: 1. One volume percent oxygen, balance nitrogen, and 2.. Tour volume percent oxygen, balance nitrogen. 6 P vs & sud. M en sn k wmu -w.< n nm-ts ~~..gA L If kedSf/uY$D'[N% rome ~M,qw.a %wTIr Gle $r'afe*?2de, r'b$fddeY t fil Q - ma usa.gus s kr call for declaring the channel inoperable. SAN ON0fRC-UNIT 2 3/4 3-73 ~ ~Aw&kn, s w's..m....see.

f. / I r r, - f lis'.. J I ABI[ 4.11-1 RAD 10ACTIVI IIQU10 WA51f SAf1PLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD) Type frequency frequency Analysis (pCi/ml)a A. Batch W3ste P P ,7 5x10 Each Batch Each Batch Principa} Gamma Release'\\. Emitters d 'J anks -6 1-131 1x10

1. Primary P1' ant

, Makeup Storage -5 P M Dissolved and 1x10 - Tanks "\\'2. Radwaste Primary One Batch /M Entrained Gases (Gamma emitters) Tanks -5 $k803ry Tanks D Each Batch Compos te H-3 1x10 7

4. Miscellaneous Gross Alpha 1x10 Waste Condensate Monitor Tanks 5x10'O
5. Neutralization P

Q Sr-89, Sr-90 b Sump Each Batch Composite -6 Fe-55 1x10 m ~7 5x10 D W Principa} Gamma B. Continuous' C Releases Grab Sample Composite Emitters -6

1. Steam Generator I-131 1x10 Blowdown 1x10'b
2. Turbine Building M

M Dissolved and Sump Grab Sample Entrained Gases (Gamma Emitters) l

3. Miscellaneo s i

Waste Eva ora r -5 Grab ample Compo ite H-3 1x10 c Condensat 'I Gross Alpha 1x10' 4.~~5 alt Water Discharge From -8 l Component Cooling Heat 0 Q Sr-89, Sr 90 5xM c Exchanger Grab Sample Composite -6 Fe-55 ix10 l ~ b 7 W 1/d 11-7 l (AN ONOTRf-IINIT 2 {

/ QQ][{.nlm../C0py 7 TABLE 4.11-1 (Continued c .o.a TABLE NOTATION ' ~b. A ccmposite sample is one in which the quantity of liquid sampled is pr:p r.icnal to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. c. To be representative of the quantities and concentrations of radioactive materials in liquid effluents, samples shall be collected tentinuously in proportion to the rate of flow of the effluent stream. Prior to analyses, all samples taken for the W.. composite shall be throughly mixed in order for the composite sample to be representative of the effluent release. d. A batch release is 1.he discfrarge of liquid wastes of a discrete volume. Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed, by a method described in the ODCM, to assure representative sempling. e. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release. f. The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141, and Ce-144. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and t e a t ed l smplirq of the Miscellaneous Waste Evaporato } h. r. if the 03ndensate Manitof Tank Bypass Valve ( l k.'. fied locked closed at least once per 31 days. 7 + .m.. >.... i .A. .~ % - ~ / 9 e F - + e 4 e ~ ,/J u 4- = - - -

TAouE 4.11-2 c RADIOACTIVE GASEOUS W4STE 'AMPLING AND ANALYSIS PROGRAM S w w o5 Minimum tower Limit of O Sampling Analysis Type of Detection QLD) Gaseous Release Type. Frequency Frequency Activity Analysis (pCi/ml) P P 9 5 A. Waste Gas Storage Each Tank Each Tank Principal Gamma Emitters lx10 4 .4 . Tank Grab m < 4 ample ~ B. Containment P' h fP e P Principal Gamma Emitters 1x10 4 b 42 inch ch Purge,c Each Purce H-3 1x10 6 b h

  • M g

Principal Gamma Emmitters 1x10

  • 8 inch Grab Sample si_3 1x10 6,

D D C.

1. Condenser M

M Principal Gamma Emitters 9 1x10 4 Evacuation Grab l{ System Sample - H-3 1x10 s

2. Plant Vent b

b W,e y 7 Stack f D. All Release Types - Ccatinuous W'1 I-131 1x10 12 as listed in B and Sampler Charcoal i ~ Sample I-133 1x10 18 C above - I W" Principal Gamma Emitters Co'ntinuous 9 1x10 81 Sampler Particulato (I-131, Others) l Sample i F. _- f, Contiriuous M Gross Alpha 1x10 11 .- l 1 Sampler Composite l Particulate i Sample I !i Continuous Q Sr-89, Sr-90 ' 1x10 11 Sampler Composite Particulate Sample ' ~ Continuou[ Noble Gas Noble Gases 1x10 s Monitor Monitor Gross Beta or Gamma l

v 'f TABLE 4.11-2 (Continued) j \\ ( TABLE NOTATION b. Analyses shall also be performed following shutdown, startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period. c. Tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. d. Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours after changing (or after removal from sampler). Sampling shall also be performed at least once per 24 hours for at least 7 days following each shutdown, startup or THERMAL POWER changs exceeding 15 percent of RATED. THERMAL POWER in one hour and analyses shall be completed within 48 hours of changing. When samples collected for 24 hours are analyzed, the corresponding LLD's may be incre,ased by a factor of 10. e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area, whenever spent fuel is in the spent fuel pool. T. The ratin of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate g calculation made in accordance with Specifications 3.11.2.1, 3.11. 2. 2 and 3.11. 2. 3. - g. The principal. gamma emitters for which the LLD specification applies exclusively are the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, 2n-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. Thjs list does not mean that only these nuclides are to be detected and reported. Other peaks which are measureable and identifiable, together with the above nuclides, shall also be idantified and reportied. k && A f 9trfkl C b5 N Y rt

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