ML20207P564

Rev 1 to Radiation Monitoring Sys (Rms),Insufficient RMS Detection Equipment

ML20207P564
Person / Time
Site:	Sequoyah
Issue date:	12/20/1986
From:	Damon D TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20207P454	List: ML20207P453 ML20207P468 ML20207P564 ML20207P573 ML20207P578 ML20207P583 ML20207P600 ML20207P604 ML20207P608 ML20207P629 ML20207P641 ML20207P647 ML20207P650 ML20207P653 ML20207P654 ML20207P656
References
229.11(B), 229.11(B)-R01, 229.11(B)-R1, NUDOCS 8701160249
Download: ML20207P564 (72)

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{{#Wiki_filter:n TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) ~, " < SPECIAL PROGRAM REPORT TYPE: SEQUOYAH ELEMENT REVISION NUMBER: 1 TITLE: RADIATION MONITORING SYSTEM (RMS) Insufficient RMS Detection Equipment PAGE 1 0F 36 k REASON FOR REVISION: Incorporation of TVA Comments. ( f l 4 k PREPARATION E PREFARED BY: /$/ A k (.I-( ' SIGNATURE ' DATE REVIEWS

AEK, VIEW COMMIT E h

5 $r _ /2 986 V SIGNATURE (/' / / DATE TAS: SIGNATURE DATE Y CONCURRENCES 3 [ I24#/% e CEG-H: d.N d l2-10-b6 j SRP: i SIGNATURE DATE SIGNATURE DATE q APPROVED BY: b ECSP MANAGER DATE MANAGER OF NUCLEAR POWER DATE f: CONCURRENCE (FINAL REPORT ONLY) 0701160249 870109 PDR ADOCK 05000327 P PDR

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) "o SPECIAL PROGRAM REVISION NUMBER: 1 h PAGE 2 0F 36 1. CHARACTERIZATION OF ISSUE (S): Concern: Issues: IN-85-144-001

a. Quantity of radiation detection "CI does not feel there is enough equipment in the plant is deficient.

radiation detection equipment in the plant; specifically, on the

b. Radiation monitoring system (RMS) for' radioactive process piping process piping RMS needs more systems (CI did not specify system radiation detection equipment.

1. 's) in Unit 1 and in the shield building vent stack for Unit 1.

c. Shield building vent stack RMS does CI feels Unit 1 shield building not have enough RMS equipment to meet vent stack needs more radiation current federal guidelines.

monitoring equipment to meet federal guidelines. Construction department concern. CI has no further information." 2. HAVE ISSUES BEEN IDENTIFIED IN ANOTHER SYSTEMATIC ANALYSIS? YES NO X e~ Identified by N/A Date N/A Documentation Identifiers: None. 3. DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN ELEVENT. No document or tag numbers were stated in the concern. The concern specifies " radiation detection equipment" on the " radioactive process piping." The evaluator concludes that the EC is referring to the Process and Effluent Radiological Monitoring and Sampling Systems (PERMSS) as well as the Area Radiation Monitoring System (ARMS). The specific reference to "the shield building vent stack" radiation monitoring system causes it to be treated with special emphasis in this evaluation. 4 1080d - 12/19/86 ^

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11(B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 3 0F 36 4. INTERVIEW FILES REVIEWED: Both the expurgated and the working files of concern IN-85-144-001 were reviewed. From the expurgated file: a. K-form dated 08/15/85 was assigned to NSRS to investigate on 08/19/85 b. " File Screening Sheet" referred this concern to ECTG for resolution or investigation (dated 06/24/86) From the working file: a. Form "D," "WBN Special Program on Employee Concerns 'K'-Form Review for Generic Applicability," states concern is generic to SQN because of similar design; further information is needed to determine applicability to BFN and BLN (dated 12/08/85) h b. Form "G-A" states concern generic to several systems at WBN. SQN had similar designs (dated 02/02/86) 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT: See Appendix A. 6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA? See Appendix A. 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSION 5 RELAltU 10 ELEMENI. See Appendix A. f_ h 1080d - 12/19/86

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 4 0F 36 8. EVALUATION PROCESS: a. Reviewed the SQN FSAR to establish detector quantity, type, range sensitivity, and related requirements of each installation. b. Reviewed the requirements of Safety Evaluation Report and Supplements to establish initial SQN RMS compliance. c. Established present regulatory requirements for RMS. d. Reviewed FSAR Sections of other PWR plants to establish presently accepted RMS practices in the nuclear power industry. e. Reviewed TVA design documentation to determine the SQN RMS level of compliance to current TVA guidelines-and commitments. f. Compared the results of steps a, b, c, and d against e to evaluate the concern. g~ 9. DISCUSSION, FINDINGS, AND CONCLUSIONS: Chronology: This concern was raised initially on WBN in August 1985 and was referred to the ECTG for resolution in June 1986. It was determined to be generically applicable to SQN because of similarity in equipment procured and general system design. (It may also be generic to other TVA units.) No specific investigative, action was taken prior to the concern's assignment to the ECTG for resolution. Interpretation and Scope The CI's use of the term "enough" in the context of "not... enough radiation detection equipment in the plant" and the later phrase "needs more radiation monitoring equipment" demonstrates an explicit concern as to quantity. At no point in the concern does the CI express qualitative reservations about the equipment in place. Therefore, the evaluator assumes that those parameters relating to the quality of the equipment in question (i.e., sensitivity, range, response time, seismic hardness, environmental qualification, etc.) are not issues here. Nevertheless, to achieve as complete verification as possible, certain key qualitative parameters will be addressed. ( 1080d - 12/19/86 c

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) ~ 'o SPECIAL PROGRAM 1 REVISION NUMBER: g PAGE 5 0F 36 Beyond the general concern as to overall quantity, the CI is more specific about " radioactive process piping systems." This suggests that the CI feels there are not enough process liquids detectors. The evaluator has assumed that the main steam, steam generator blowdown, and condenser air ejection also qualify, under certain assumed leakage conditions, as " radioactive process piping systems." The term is further expanded by assumption to include ventilation (e.g., " process") duct (e.g., " piping") monitors. The concern, as expanded by this interpretation, applies to the complete Process and Effluent Radiological Monitoring and Sampling System (PERMSS). This " system" is actually a grouping of sampling / monitoring subsystems located at each release point and on selected processes that have a potential for carrying radioactive inventory. The CI is also quite specific about an insufficient quantity of radiation monitoring equipment on the Unit 1 Shield Building Vent Stack "to meet federal guidelines." This presents a licensing compliance issue both as to the original system and the newer federal requirements for Post Accident Monitoring (PAM). Through the use of the term " radiation detection equipment," it is (c possible that the concern may also relate to the Area Radiation Monitoring System (ARMS). The PERMSS and the ARMS combined constitute the SQN Radiation Monitoring System (RMS) whose overall purpose, as defined by the relevant regulatory criteria and guidance, is to monitor various process streams (gas, steam, or water) and plant areas to give early warning of degraded conditions that might present health hazards to plant operators or to the I public (App. A, 6.a, b, c, d, e, f, g, h). Using the above interpretations, the evaluator reviewed the entire, SQN RMS. Two different approaches were used; first, a general comparison with radiation monitoring practices at other PWRs, and, second, a verification review of the design criteria, design i drawings, and FSAR against the SER findings. )p SQN PERMSS Description All PWRs have essentially the same basic sources of radioactivity in their process piping. Generally, any system that communicates 3 with the reactor coolant system (RCS) or " primary loop" is presumed to carry radioactive inventory. This is the case whether the communication is by direct piping connection or through heat exchanges and steam generators where leakage is presumed, k-1080d - 12/19/86 e iL

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (8) SPECIAL PROGRAM REVISION NUMBER: 1 b PAGE 6 0F 36 In addition, those processes that treat liquid waste collected from various points throughout the plant are also presumed to carry radioactive inventory. All such processes are either sampled or monitored, sometimes both, to ensure that they meet federal design criteria (App. A, 6.b, c and d), operational standards (App A, 6.h, 1), and regulatory guidelines (App. A, 6.g, h, and s). At SQN the following processes are considered to have a reasonable potential for carrying radioactive material in sufficient concentrations to warrant radiation monitoring: Reactor Coolant Chemical and Volume Control (Boron Recirculation) Residual Heat Removal Steam Generator Blowdown Condenser Vacuum Pump Exhaust Essential Raw Water Cooling Component Cooling fuel Pool Containment Building Drain Sump Sample Station Sump Discharge Waste Disposal System Liquid ( Since radioactive vapors can escape from the above processes, certain sections of the plant's ventilation system must be monitored to prevent release. These monitors will vary from plant to plant depending on plant arrangement, ventilation system design and number of release points. At SQN the following ventilation systems are monitored to control the release of airborne radioactivity: Shield Building Vent Auxiliary Building Vent Service Building Vent Containment Building Compartments (two levels) Containment Building Purge Air Containment Building Personnel Hatch Post-Accident Sample Room In addition to monitors whose basic purpose is release control there are certain unique purpose monitors. designed for unusual occurrences and accidents. At SQN these monitors are: Main Control Room Air Monitors Main Control Room Air Intake Monitors As will be demonstrated later, monitoring of the above systems is directly consistent with the RMS practices at other licensed and ~, operating PWRs. 1080d - 12/19/86

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM ' + REVISION NUMBER: 1 b PAGE 7 0F 36 The SQN PERMSS is generally described in SQN FSAR Section 11.4 with particular attention to important parameters (sensitivity / range, i detector type, background level, etc.) listed in Tables 11.4.2-1 (Liquid) and 11.4.2-2 (Gaseous). These tables are attached as Attachments 1 and 2 for easy reference. It should be noted that the FSAR description (App. A, 5.a) is out of date with respect to the the Design Criteria (App. A, 5.V) and the design drawings (App. A,5.ii,jj,kk,ll,mm). Reading the'FSAR by itself could lead to a conclusion that "there is not enough radiation detection. equipment" to meet current " federal guidelines." The FSAR should be updated. SQN PERMSS Coraparison with Other PWRs An independent verification of SQN PERMSS adequacy was performed by comparing the SQN system monitored with equivalent systems for a standardized PWR plant (SNUPPS), a remote dry site PWR (Palo Verde), and a shoreline PWR unit close to a metropolitan area (San Onofre). The data used for this comparison are outlined in the FSARs for each of these plants. The relevant tables from these FSARs are attached as Attachments 5, 6 and 7 for easy reference. ( Following the incident at Three Mile Island the NRC published additional monitoring requirements that necessitated _ modifications and additions to the SQN RMS. These are not reflected in the FSAR but appear on the design drawings and in the current version of the SQN RMS Design Criteria (App. A, 5.V). The tables from the design criteria are attached as Attachments 3 and 4 should be used with the FSAR tables to get a full picture'of the present system. The~ quantity of detection equipment and its location within each plant depends greatly upon the operating procedures, plant arrangement, health physics program, and process design. Comparing the data in these appendices shows that SQN monitors essentially the same systems, has monitors at all release points, and has an equivalent number of special purpose monitors. While variations in individual plant design prevent direct line by line co relation, an objective professional judgment of SQN equivalence is easily drawn f by the commonality of the basic processes monitored. or example, all plants must comply with the requirement that all potentially radioactive release paths must be sampled and monitored. The number of release paths at each plant establishes the cJantity of monitors required, but the release limits are establit.hed by federal standards common to all plants. Therefore, to ensure SQN compliance with these standards, the most key equipmer.t,sarameter nucleonic nature of the release effluent) g the predominant (i.e. sensitivity to trace isotopes settin were compared, ,l 1080d - 12/19/86 i l

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11(B) P '** SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 8 0F 36 RMS sensitivity is established by the physical and chemical collection efficiency of the sampling medium and by the detector's ability to sense the radiation of the trace nuclides in question above a certain background..The clearest-statement of sensitivity [ is in terms of the systems minimum detectable concentration to a specific isotope. Usually the isotopes identified are those that I have the most abundance and, thereby, set the nuclear characteristics of the gross mixture. (Isotopes rarely occur individually). These are called the " trace isotopes". Often because of their biological significance certain isotopes are sampled or monitored individually even though they don't constitute i a predominant part of the gross mixture. These factors are common to SQN and the other plants reviewed. The following table compares SQN sensitivity with similar PWR units: General Comparison to Other PWR PERMSS [ Parameter SQN PVNGS SONGS SNUPPS Gas I-Trace Isotope-Kr-85 Kr-85 Xe-J33 Xe-133 Sensitivity

• 10-6 10-6 10-10-/

Particulate Trace Isotope Cs-137 Cs-137 Cs-: 37 Cs-137 Sensitivity

• 10-9 10-9 10- 2 10-12 i

Halogen Monitors l Trace Isotope I-1 31 Ba-133 I-1 31 1-131 Sensitivity

• 10-9 10-9 10-II 10-II~

f. Process Liquids Monitors Trace Isotope I-1 31 Cs-137 Cs-137 Cs-137 Sensitivity

• 10-6 10-6 10-7 10-7 i

j

• All sensitivities are given in terms of uCi/cc concentrations of j

the trace isotopes in question. From this general comparison, the SQN PERMSS appears to be i generally equivalent to other PWRs. Differences in sensitivity may be due to different background levels, differences in what is );. considered a readable signal above background noise or trade-offs between response time and sensitivity level. Variations in t-i individual plant designs are also reflected in the PERMSS unique to each plant. Even with these considerations, no obvious variance that would identify deficiencies in the SQN PERMSS is evident. 1 1080d - 12/19/86

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 b PAGE 9 0F 36 The sensitivity differences above do not necessarily mean that SQN is less sensitive than SONGS or SNUPPS. To understand why requires some explanation about how sensitivity statements are derived and specified. Sensitivity of RMS equipment is usually specified in terms of'a signal-to-noise ratio. The signal is produced by sensing the disintegration rate of_the sampled isotope (s) and the noise is generated by naturally occurring radiation sources (i.e., cosmic, radon-thoron gases, etc.) radiation fields in the plant and electronics noise (i.e., thermionic photo-cathode emissions, electromagnetic interference, micro-phonics, etc.) In order for a signal to be " readable" it must rise above the noise level by a certain factor. Sometimes this is specified as " net signal equal to background [ noise]" where a 100 count per minute (CPM) background would require a sufficient concentration of the sampled isotope to generate a 100 CPM signal. Therefore, if the background' noise level rises, the signal necessary to overcome it rises as well, and a higher isotopic concentration is necessary making for a less sensitive monitor. .., s t It can be seen, therefore, that a monitor having a sensitivity of, 10-7 uCi/cc in a 0.1 mR/hr background would only have a say5uCi/ccsensitivityifthebackgroundwere1.0mR/hr. 10-The " natural" background is usually established at 0.1 mR/hr and many _ plants (e.g., SONGS) attempt to locate their monitors in environments where the plant induced background can be disregarded. Other plants (e.g., PVNGS, SQN) want to have more latitude in the final location of the monitor and so they will assume a plant induced background of 1.0 mR/hr. and accept a lower. sensitivity statement even though the monito*rs may be identical. Another variable in background noise may be the amount of margin the designer-wants in avoiding spurious alarms due to environmental i conditions. In monitors using photo-multiplier tubes (i.e., scintillation detectors), the background noise due to thermionic emission from photo cathodes can rise exponentially with linear changes in temperature. Therefore, if temperature variations are to be expected, the designer may choose to establish set point or sensitivity at signal levels where this is not a factor. This too would call for a lower sensitivity statement even though the monitors were identical. !' ( i 1080d - 12/19/86 e

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM 0 - REVISION NUMBER:. 1 I h PAGE 10 0F 36 The manner in which the signal-to-noise ratio is specified also affects sensitivity. The " net signal equal to background" statement noted earlier is very conservative. Less conservative approaches are where the standard statistical deviation of the background is multiplied by a certain factor to achieve a statistical. confidence level. For example, the factor 2 would provide the "95% Statistical Confidence Level (SCL)." i Using this method, if one monitor had a 100 CPM background on a one (( minute sampling base then the standard deviation would be about 10 3: CPM anc. the "95% SCL" about 20 CPM. The isotopic concentration l necessary to produce this is only 20 per cent of the concentration necessary to produce a " net signal equal to background." Thus the [ "95%" SCL monitor would appear to be five times as sensitive even j though the equipment was identical. I l Other factors such as sampling and response times can affect sensitivity statements. For example, the same fixed filter particulate monitor could have a sensitivity of 10-10 uCi/cc if tohaveasensitivityof10gefor12 minutes,butcouldbesaid it sampled a long lived isot uCi/cc if it sampled for 2 hours. 3 t For these and several deeper technical reasons (e.g., secular 4 equilibrium where decay times approach sampling times) the very 4 same monitors can have sensitivity statements that differ by a decade or more. j U The detection equipment used in radiation monitoring systems, which is what really establishes. base sensitivity, is all essentially the 1 same. Sensitivity levels in field applications are limited more by [ physical variables than by the equipment itself. These physical variables are common to all plants and, therefore, the equipment used is common as well. The only real differences occur in the J methods used to describe the systems. With these considerations in mind, the evaluation team finds that 4 the SQN monitors seem directly consistent with PVNGS and acceptably ? close to SONGS, and SNUPPS to be considered equivalent. In all cases, the monitors sensitivities are well in excess of those [i required by the federal guidelines in the following section. 1 1 1 A s i j 1080d - 12/19/86 b

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 0 PAGE 11 0F 36 Federal Guidelines The most definitive statement of RMS compliance with " federal guidelines" was the NRC's Safety Evaluation Report (SER). The suggestion in the concern that there is not "enough radiation detection equipment... to meet federal guidelines" presents a basic license compliance issue. To assess this, the evaluators first had to establish what the federal guidelines were. This necessitated review of the relevant documents listed in Appendix A, Section 6. This review resulted in the following general summary. l The operational limits placed on release of radioactive materials are established by 10CFR20 (App. A, 6.f). This is to be contrasted with Section 50.34a of 10CFR50 (App. A. 6.a) which establishes the general design guidance to be used to " maintain control over radioactive materials in gaseous and liquid effluents" and to keep " levels of radioactive materials in effluents to unrestricted areas as low as reasonably achievable." Appendix A of 10CFR50 sets out three general design criteria in this regard (App. A, 6.b, c and d): " Criterion 60 - Control of releases of ( radioactive materials to the environment. The nuclear power unit design shall include means to control suitably the release of radioactive materials in gaseous and liquid effluents and to handle radioactive solid wastes produced during normal reactor operatica, including anticipated operational occurrences. Sufficient holdup capacity shall be provided for retention of gaseous and liquid effluents containing radioactive materials, particularly where unfavorable site i environmental conditions can be expected to impose unusual operational limitations upon the release of such effluents to the environment. " Criterion 63 - Monitoring fuel and waste storage. Appropriate systems shall be provided in fuel storage and radioactive waste systems and associated handling areas (1) to detect conditions that may result in loss of residual heat removal capability and excessive radiation levels and (2) to initiate appropriate safety actions. k 1080d - 12/19/86 ~

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM + REVISION NUMBER: 1 PAGE 12 0F 36 " Criterion 64 - Monitoring radioactivity releases. Means shall be provided for monitoring the reactor containment atmosphere, spaces-containing components for recirculation of loss-of-coolant accident fluids, effluent discharge paths, and the plant environs for radioactivity that may be released from normal operations, including anticipated operational occurrence, and from postulated accidents." Appendix I of 10CFR50 establishes numerical guidelines for the term "as low as reasonably achievable" (ALARA). Generally, the Appendix I guideline limits are estimated annual doses of 3 millirems (total body) or 10 millirems (any organ) for liquid effluents, an estimated annual air dose of 10 millirads (gamma), 20 millirads millirems (gaseous effluent estimated annual external dose of 5 (beta),or total body). Because of their chemical tendencies to concentrate in the thyroid, the iodine isotopes are singled out and limited to a 15 millirem limit exposure'to any organ. This applies to particulate isotopes as well. The concluding statement of the Annex to Appendix I establishes.a 5 millirem total body or any ,I organ dose limit on liquids released from multiunit sites or a total quantity of 5 curies / year per reactor (excepting tritium and dissolved gases). For gaseous effluents from multiunit sites, the 10 millirad (gamma), 20 millirad (beta), and 15 millirem (iodines and particulates) dose limits of Appendix I are confirmed by the Annex. Appendix I also establishes cost-benefit guidelines for containing and processing radioactive inventories at $1,000 per man rem, total body and thyroid. l Of the relevant Regulatory Guides, Reg. Guide 1.21 (App A, 6 9) most directly addresses implementation of the 10CFR20 operating release limits. Reg. Guide 1.21 requires monitoring of all "significant paths for release of radioactive material" to demonstrate compliance. It also stipulates requirements to evaluate " performance of containment, waste treatment and effluent controls" and collection of data to " permit evaluation of . environmental impact and potential dose to the public." The most significant RMS parameters set by Reg. Guide 1.21 are the required sensitivities. For gases this is generally set at a minimum detectable concentration of 10-4 uCi/cc for being equivalent to 4 1080d - 12/19/86

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) (' SPECIAL PROGRAM REVISION NUMBER: 1 h PAGE 13 0F 36 the~10 millirad (gamma) and 20 millirad (beta) limits of Appendix I. Iodine and particulate measurements are set at the-15 millirem organ (thyroid) levels. Tritium is treated as a special caseofgaswithaminimumdetec)ableconcentrationof10-0 uCi/cc. Gross activities of 10- uCi/cc in liquids should be detectable with higher concentration limits set for individually identified gamma emitting isotopes (5 x 10-7 uCi/cc) and special case limits set for Sr-89 and Sr-90 (5 x 10-8 uCi/cc). Reg. Guide 1.97 and NUREG 0737 address the use of radiation monitoring for post accident analyses, which is treated separately later in this report. With these basic criteria as guidance, the evaluation team was positioned to independently assess the NRC SER~of the SQN RMS and either confirm or challenge its validity in support of the current license. Safety Evaluation Report (SER) SQN SER Section 11.0 established that the following design (,. parameters were applied by the NRC in assessing the SQN PERMSS: "In our evaluation of the process and effluent radiological monitoring and sampling systems, we have considered the system's capability: (1) to monitor all normal and potential pathways for release of radioactive materials to the environment, (2) to control the release of radioactive materials to the environment, and (3) to monitor performance of process equipment and detect radioactive material leakage between systems." These design parameters were compared with the federal guidelines outlined above and found to be consistent with 10CFR20, 10CFR50, and Regulatory Guide 1.21. With their analysis guided as outlined above, the NRC concluded that: " Based on the following evaluation, we conclude that the liquid and gaseous radioactive waste treatment systems for Sequoyah Nuclear Plant are capable of maintaining releases of radioactive materials in liquid and gaseous effluents to 'as low as is reasonably achievable' levels in accordance with 10 CFR Part 50.34a, and with Section II.A, II.8, II.C, and II.D of Appendix I to 10 CFR Part 50." 1080d - 12/19/86

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 k PAGE 14 0F 36 " Based on our evaluation, as described below, we find the proposed liquid, gaseous and solid radioactive waste systems and associated process and effluent radiological monitoring and sampling systems to be acceptable." Referring more specifically to monitoring and sampling equipment locations and types, the NRC stated in Section 11.2 of the SQN SER: l I "We have reviewed the locations and types of effluent and process monitoring provided. Based on the plant design and on continuous monitoring locations and intermittent sampling locations, we have concluded that all normal and potential i release pathways are monitored. We have also determined that j the sampling and monitoring provisions are adequate for J. detecting radioactive material leakage to normally [ uncontaminated systems and for monitoring plant processes which could affect radioactivity releases. On this basis, we consider the monitoring and sampling provisions to meet the requirements of General Design Criteria 60, 63 and 64 and guidelines of Regulatory Guide 1.21, ' Measuring, Evaluating, j' and Reporting Radioactivity Solid Wastes and Releases of i Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plant'". i The ability to monitor and sample, as outlined above, was carried further into the PERMSS ability to automatically terminate disallowed releases. The following conclusion was reached in Section 11.3 of the SQN SER: "Our review of the radiological process and effluent monitoring system included in provisions for sampling and 1 monitoring all normal and potential effluent discharge paths in conformance with General Design Criterion 64, for providing automatic termination of effluent releases and g assuring control over releases of radioactive materials in effluents in conformance with General Design Criterion 60 and Regulatory Guide 1.21, for sampling and monitoring plant 1 waste process streams for process control in conformance with General Design Criterion 63, for conducting sampling and analytical programs in conformance with the guidelines-in 1 Regulatory Guide 1.21, and for monitoring process and effluent streams during postulated accidents. The review j included piping and instrument diagrams and process flow diagrams for the liquid, gaseous, and solid radwaste systems and ventilation systems, and the location of monitoring points relative to effluent release points. We conclude that the applicant's radiological process and effluent monitoring b systems are acceptable." (! 1080d - 12/19/86 i

~TVA EMPLOYEE. CONCERNS REPORT NUMBER: 229.11.(B) 'i SPECIAL PROGRAM REVISION NUMBER:. 1 .7 PAGE 15 0F 36 SER VALIDATION The evaluation team used three methods to validate the above SER findings. First, the evaluation team used the current federal guidelines outlined above and applied them to the SQN FSAR description of the RMS (App. A, l' 5.a) using the same design parameters that the NRC used in deriving the SER findings quoted above. No discrepancies were found that would lead to conclusions different from the NRC SER conclusions quoted above. Second, to ensure that the NRC SER, which relied mostly on FSAR 4 statements, was supported by the actual design, the evaluation team also compared both SER findings and the SQN FSAR with the current SQN b PERMSS 0.esign Drawings (App A, 5.mm through 5.ss), the RMS procurement ); specifications (App. A, 5.cc thru 5.ff), and the SQN Mechanical j_ Instrument Tabulation (App. A, 5.00), which establishes setpoints. This review confirmed that the "as designed" SQN RMS supported the NRC

~

l. SER findings of compliance with federal guidelines. In the course of j these evaluations, it was noted that design improvements have been made to the PERMSS since the NRC filed its SER. Therefore, the initial NRC j aI-finding of adequacy has been enhanced since that time. j. The third method used to validate the NRC SER constituted an independent assessment of the current RMS design documentation (App. A, 5.cc through 5.ff and 5.mm through'5.ss) against the federal guidelines. ]. outlined above. In this review, some small discrepancies within the i design documentation were noted. For example, Design Criteria 1 SQN-DC-V-9.0 (App. A, 5.v) paragraph 3.5.2.1 stipulates that the l-Condenser Vacuum Pump Exhaust Vent Monitor is "to satisfy the requirements of Regulatory Guide 1.45." This is a physical impossibility because Regulatory Guide 1.45 requires detection of the reactor coolant pressure boundary leaks to containment and a communications path from containment to the condenser does not exist. 3 The discrepancies noted, however, did not result in RMS deficiencies 3j that would conflict with federal guidelines or invalidate the NRC's original findings of adequacy. In fact, the design documentation shows %j enhancements that would substantiate such findings more today than when originally made. d j It should be noted that the NRC SER did not review changes required following the incident at Three Mile Island. This is a different issue -i and is addressed later in this report. The investigation conducted to this point merely confirms that the present SQN RMS meets the last definitive NRC statement of acceptable compliance to " federal guidelines." This has now been established by three different methods i t' validating the SER and by independent comparison with other licensed 1 k and operating PWRs. I I 1080d - 12/19/86 L

.L TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) t SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 16 0F 36 Shield Building Vent Stack -The concern's specific reference to the " shield building vent stack" which includes normal and accident range monitors for noble gases, airborne iodine, and particulates. The shield building exhaust vents, one per unit, provide a release pathway for the containment purge, annulus purge, and emergency gas treatment systems. The evaluator compared the quantity and sensitivity of the normal SQN Shield Building Exhaust Vent Monitoring System (1-RE-90-100) with plant and monitoring systems on other representative plants that are licensed for operation. The SQN monitors were found comparable.to those of the other PWR plants studied. The following table presents the results of this comparison: Plant Quantity / Sensitivity (uCi/cc) Unit SQN 1 10-6 Kr-85 10-9 Cs-137 10-9 I-131 PVNGS 1 10-6 Kr-85 10-9 Cs-137 10-9 Ba-133 'f" SONGS 1 10-7 Xe-133 10-12 Cs-137 10-11 1-1 31 SNUPPS 1 10-7 Xe-133 10-12 Cs-137 10-11 I-131 The above differences in sensitivity are attributed to the same factors previously discussed. It should be noted that differences in plant configurations do not allow for the other plants to make use of their plant vent monitor to also monitor containment vents, as is the case at SQN. These other plants monitor containment vents separately; some with redundancy. This redundancy may be due to a particular use of RMS in post accident monitoring or, as in the case of SNUPPS, an effort to err on the conservative side to avoid future changes on several plants using a standardized design. Whatever the reasons, present regulatory requirements do not require or suggest redundancy. From the review conducted and considering the variables regarding this parameter; the table above shows that SQN has equivalence to other units and remains consistent with the NRC SER. W 1080d - 12/19/86

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) l, SPECIAL PROGRAM REVISION NUMBER: 1 h-PAGE 17 0F 36 Post Three Mile Island Changes Following the incident at Three Mile Island, the NRC published a series of guidance documents that built upon the lessons learned (App. A, 6.n) and initiated an action plan (App. A, 6.0) to institute changes. Two of these changes affected the SQN RMS; NUREG 0737 (App. A, 6.p) and Regulatory Guide 1.97 (App. A, 6.k). Each set of requirements were reviewed against the present configuration of the SQN RMS as evidenced by the design criteria, design drawing and purchase contract specification. Physical inspection of the equipment was not conducted. 6 NUREG-0737, Supplement 1 provided guidance that called for additional radiation monitoring capability (App. A, 5.f). In response, TVA added high range and wide range noble gas monitoring to the Shield Building Vent Stack RMS and extended range ARMS inside containment. TVA did not add main steam line or safety / dump valve discharge monitors. The presently installed Steam Generator Blowdown and Condenser Air Ejection monitors were considered sufficient for this purpose. TVA attempted timely response to NUREG-0737(App.A,5.m,o). ( Review of the design drawings (App. A, 5.mm thru 5.ss) and the SQN l Design Criteria for RMS, SQN-DC-V-9.0 (App. A, 5.v) confirmed follow-through on equipment changes and additions necessary to meet i NUREG-0737. The following radiation monitors are addressed affected by this latest version of the SQN Design Criteria: l Condenser Vacuum Pump Exhaust Vent Monitors Shield Building Vent Monitors Auxiliary Building Vent Monitor Main Control Room Airborne and Area Monitors Main Control Room Air Intake Monitors Containment Building Purge Air Exhaust Monitors Containment Building Personnel Hatch Monitor Post-Accident Sample Room Monitor Fuel Pool Monitors Steam Generator Blowdown Line Monitors Residual Heat Removal Line Monitors Reactor Coolant Drain Discharge Monitors Station Sump Discharge Monitor Plant Liquid Discharge Monitor Containment Building Floor and Equipment Drain Sump Discharge Monitors Containment Building Upper and Lower Compartment Monitors b 1080d - 12/19/86

y TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11'(B) SPECIAL PROGRAM REVISION NUMBER: .1 h PAGE 18 0F 36 Tables 9.0-1 and 9.0-2 of the Design Criteria are attached as Appendices E and F to augment the FSAR tables.of AppendiEes C and D. These tables show the additional RMS equipment to meet NUREG-0737, Supplement I requirements. NRC Regulatory Guide 1.97-(Rev. 2) Both NUREG 0737, Supplement 1 and Regulatory Guide 1.97 (Rev. 2) i resulted from lessons learned at Three Mile Island. Where NUREG L 0737, Supplement 1 required the addition of RMS capability, Regulatory Guide 1.97 dealt with how monitoring information was to l-be employed in following the course of an accident. These post [ accident monitoring (PAM) requirements mostly made use of instrumentation already in the plants but, in many cases, added [ requirements (e.g., seismic and environmental qualification) j necessitated new procurement at many f acilities, including SQN. {. With the addition of the NUREG 0737, Supplement 1 equipment outlined j-above, SQN had sufficient RMS equipment to meet these minimum requirements of Regulatory Guide 1.97. I In March 1982, TVA submitted a timely response to the PAM ) h,. Requirements of the Regulatory Guide 1.97 (App. A, 5.q). Correspondence and documentation following the March 15, 1982 submittal (App. A, 5.u, jj, tt, uu, vv) indicates that TVA has programs in place that are making assessments and modifications to what will be implemented at SQN to meet Reg. Guide 1.97, Rev. 2. j' Final resolution and implementation of this issue are being deferred ] from September 1987 to the SQN Unit 2, Cycle 4 outage (App. A, 5.vv) and are not an issue in this concern. ARMS Comparison With Other PWRs While the concern clearly refers to the PERMSS, it did not specifically exclude the ARMS. Because the ARMS detects only mean gj gamma radiation levels to preestablished guidelines limits, the type 4 of equipment used is fairly uniform from plant to plant. The quantity and location of such detection equipment, however, is unique to plant type (BWR or PWR) and individual plant procedures y and arrangements. Therefore, comparison of the SQN ARMS to other units would not provide fully verifiable conclusions. However, a g 3, general correlation as to equipment parameters is possible. l The SQN ARMS is described in SQN FSAR Section 12.1.4. The equipment a described has the same features commonly found in other state of the art systems (e.g., G-M detectors, built-in check sources, j five-decade range, alarms, annunciation, recording, etc.). .1 ] 1080d - 12/19/86 m

~ TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11.(B) SPECIAL PROGRAM REVISION NUMBER: 1 (' : PAGE 19 0F 36 The a'dequacy'of the ARMS was reviewed in Section 12.0 of the-SQN SER. " Twenty area radiation monitors are provided throughout the plant in areas in which personnel may routinely work without direct health physics supervision and in areas where their [ sic] is a possibility of noble gas activity in concentrations that are a significant fraction of those given in 10 CFR Part-20, Appendix B, Table I. Additionally, two monitors provide for monitoring near the containment air locks and two monitors provide for personnel safety during fuel loading and refueling. The monitors are of sufficient. sensitivity to detect minor ratemeters and local and control room alarms. Local alarms are audible and visible. Instrumentation calibration checks will be performed, and dose rate levels will be recorded, in the control room. " Based on the location of area monitors, their sensitivity and range, and their alarm annunciation and recording devices, we conclude that the area monitoring program will provide satisfactory radiological protection to inplant personnel." r( The number of monitors used at SQN (20) was a bit less than at other units (see attactments). This could be due to differences in plant arrangements operating procedures and health physics programs. For example, San Onofre has 25 monitoring locations identified. Palo Verde had only 12 "non-ESF" area monitors and 4 "ESF" monitors. This is roughly equivalent to SQN, however, Palo Verde also makes extensive use of area monitors for PAM. This unique application of an additional 27 monitors is not germane to SQN. Based on this review the evaluation team could not establish any RJ ence that would conflict with the above NRC SER finding. id The R4S has "enough radiation detection" to " meet federal guidelines." g Findinas: The SQN RMS has sufficient detection and sampling capability a. [ to meet the requirements of 10CFR20,10CFR50 (including both Appendix A and Appendix I), Regulatory Guides 1.21,1.07(Outqg

6. 2 and "n. 2b 8.8, 8.10, NUREG 0737 and NUREG 0737, Supplement 1.

The SQN RMS compares favorably with equivalent systems at other licensed and operating PWR's. The SQN RMS also adopts presently accepted industry practices in its design requirements. The SQN FSAR has not been updated to accurately reflect the additions, modifications, and improvements made to the SQN RMS since TMI. b 1080d - 12/19/86 l

TVA' EMPLOYEE CONCERNS REPORT NUMBER: '229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 C' -PAGE 20 0F 36 b. The present process piping RMS, including ventilation systems, monitor all systems having a reasonable potential for radioactive inventory as well as all release paths. This is consistent with present licensing requirements for SQN and the NRC SER.which remains valid even though it does not consider the improvements made since it was filed. c. The Shield Building Vent Stack RMS has sufficient equipment to meet 10CFR20,10CFR50 and Regulatory Guide 1.21 requirements. It has been modified and expanded to meet NUREG 0737 and NUREG-0737 Supplement 1 post-TMI requirements.

== Conclusion:== The concern is not valid. The present SQN RMS meets the normal operating requirements of 10CFR20,10CFR50, including both Appendix A and Appendix I, and Reg. Guide 1.21. The validity of the initial NRC SER supporting the SQN operating license is confirmed,= idid. The present SQN RMS, as modified and expanded since TMI, meets the requirements of NUREG 0737 and NUREG 0737, Supplement 1. h 10. CORRECTIVE ACTION (Later) i- .l f s 1080d - 12/19/86 1 4

Y, TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM-REVISION NUMBER: 1 h PAGE 21 0F 36 APPENDIX A 5. DOCUMENTS REVIEWED RELATED TO THE ELEMENT: a. SNP FSAR Sections 11.4, " Process and Effluent Radiological Monitoring and Sampling System" 12.1.4, " Area Monitoring" b. SQN Safety Evaluation Report, (03/79), Supplement 1, (02/80), Supplement 2, (08/80) c. 10CFR50, " Domestic Licensing of Production and Utilization Facilities," Appendix A, Appendix I d. 10CFR20, " Standards for Protection Against Radiation" e. NRC Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous ' hd Effluents from Light Water Cooled Nuclear Power Plants," Revision 1, June,1974 - 1.45, " Reactor Coolant Pressure Boundary Leak Detection System," Revision 0, May 1973 1.97, " Instrumentation to Follow the Course of an Accident," R2, (12/80) 8.8. "Information Relevant to Ensuring that Occupational Radiation Exposures Will Be as Low as Reasonably Achievable" l 8.10, " Operating Philosophy for Maintaining Radiation Exposures as Low as Reasonably Achievable (Nuclear Power Reactors)" f. NUREG-0737, Supplement 1, " Clarification of TMI Action Plan Requirements," (11/80), Section II.F.1, " Additional Accident Monitoring Instrumentation" 9 San Onofre Nuclear Generating Station Units 2 and 3, FSAR Section 11.5, Table 11.5-3 1 h. Palo Verde Nuclear Generating Station, Units 1, 2 and 3, FSAR Section 11.5, Table 11.5-1 { 1 1080d - 12/19/86

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 22 0F 36 APPENDIX A (cont'd) 1. StandardizedNuclearUnitPowerPlantSystems(SNUPPS),FSAR Section 11.5, Table 11.5-4 j. Letter from L. M. Mills, TVA, to D. Vassallo, NRC, No. A27 7910311013, (10/31/79) k. Letter from L. M. Mills, TVA, to L. S. Rubenstein, NRC, A27 800125 019, (01/25/80) 1. Letter from L. M. Mills, TVA, to L. S. Rubenstein, NRC, NEB 800404 588, (04/02/80) m. Letter from L. M. Mills, TVA, to A. Schwencer, NRC, A27 810212 017, (02/12/81) n. Letter from M. R. Wisenburg, TVA, to E. Adensam, NRC, A27 810701021, (07/01/81) o. Letter from L. M. Mills, TVA, to E. Adensam, NRC, .s D A27 810904 019, (09/04/81) p. Letter from L. M. Mills, TVA, to E. Adensam, NRC, NEB 811113 627, (11/06/81) q. Letter from L. M. Mills, TVA, to E. Adensam, NRC, A27 820315 096, (03/15/82) r. SQN Employee Concern 230.5, "HVAC Design - Radioactivity in the CDWE Building" s. TVA Conference Notes (B43 860723 902), " Post Accident Monitoring System," (07/02/86) t. TVA memo from B. Hirmanpour to SQN Files, (B25 860909 015), "SQN Accident Monitoring Meeting of August 27, 1986," (09/09/86) u. Letter, J. O. Vantrease, Impell, to G. W. Painter, TVA, " Revision 1 to Proposal for Regulatory Guide 1.97, Rev. 2, Compliance Program," (10/13/86) v. TVA Detailed Design Criteria No. SQN-DC-V-9.0, "Sequoyah Nuclear Plant Radiation Monitoring System," R2 (07/14/86) k 1080d - 12/19/86

I., TVA EMPLOYEE CONCERNS REPORT NUNCER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: I h PAGE 23 0F 36 APPENDIX A (cont'd) w. TVA Design Criteria No. SQN-DC-V-9.0, "Sequoyah Nuclear Plant Radiation Monitoring System," R1 (03/10/86) x. TVA Mechanical Design Guide DG-M18.7.1, " Radiation Protection (ALARA) Design Guidelines," (11/20/81) y. TVA Mechanical Design Guide DG-M18.7.11, " Radiation Protection Features for Nuclear Plant Accidents," (05/31/83) z. U. S. Nuclear Regulatory Commission, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations." USNRC Report NUREG-0578, July 1979, Recommendation 2.1.8.b. aa. American National Standards Institute, " Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities," American National Standard ANSI N13.1-1969, February 1969. bb. U. S. Nuclear Regulatory Commission, " Discussion of Lessons Learned Short Term Requirements," letter from H. Denton, h7 (NRC),toAllOperatingPlants,fl0/30/79) cc. TVA Contract J2-826848, " Isokinetic Stack, Sampling Station," Air Monitor Corporation (12/10/79) dd. TVA Change of Contract 72C61-92759, "Radiatior. Monitors," General Atomic Company (12/12/80) ee. TVA Purchase Requisition Number 829854, " Emergency Purchase - Effluent Radiation Monitors," (09/22/82) ff. TVA letter to General Atomic Company, " Contract 72C61-92759 - Sequoyah and Watts Bar Nuclear Plants - Radiation Monitors - PA letter No. 5," (01/14/81) gg. Letter from D. G. Eisenhut, NRC, to All Operating Nuclear Power Plants, (09/13/79) hh. Letter from H. R. Denton, NRC, to All Operating Nuclear Power Plants (10/30/79) ii. Regulatory Guide 1.97, " Instrumentation to Follow the Course of an Accident," Rev. 3 (08/83) b 1080d - 12/19/86

M*m ~

• TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)

SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 24 0F 36 APPENDIX A (cont'd) jj. TVA OE Calculation SQN-SQS4-0052, "PAM Variable Determination in Accordance with Reg. Guide 1.97, R2 (Types A, B, & C (07/30/86) kk. TVA OE Calculation SQN-SQS4-0068, " Type D & E Variables in Accordance with Reg. Guide 1.97, R2" (09/11/86) mm. SQN TVA Drawing 45N690: -1 R10 " Wiring Diagrams Radiation Monitoring System, Schematic Diagrams Sheet 1" -2 R12 " Wiring Diagrams Radiation Monitoring System, Schematic Diagrams Sheet 2" -3 R6 Wiring Diagrams Radiation Monitoring System, Schematic Diagrams Sheet 3" -4 R1 " Wiring Diagrams Radiation Monitoring System, Schematic Diagrams Sheet 4" nn. SQN TVA Drawing Series 47A052, " Mechanical Seismic Supports - Radiation Monitoring and Sampling" co. SQN TVA Drawing 47B601-90-0 " Mechanical Instrument Tabulation" pp. SQN TVA Drawing Series 47W600: -100 R13 " Mechanical Instruments and Controls" -101 R6, " Mechanical Instruments and Controls" -102 R10, " Mechanical Instruments and Controls" -103 R4, " Mechanical Instruments and Controls" -104 R19, " Mechanical Instruments and Controls" -105 R10, " Mechanical Instruments and Controls" -106 R14, " Mechanical Instruments and Controls" -107 R9, " Mechanical Instruments and Controls" -108 R0, " Mechanical Instruments and Controls" -109 R4, "Multiline Shield Building Seals" -110 R3, " Mechanical Instruments and Controls, Pneu & Elec Test Bench" -111 R3, " Mechanical Instruments and Controls, Pneu i. & Elec Test Bench Det" -112 R1, " Mechanical Instruments and Controls, Pneu & Elec Test Bench Det" -301 R4, " Mechanical Instruments and Controls" -302 R2, " Mechanical Instruments and Controls" b 1080d - 12/19/86

V, TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 I PAGE 25 0F 36 APPENDIX A (cont'd) 1 qq. SQN TVA Drawing Series 47W610: 1 R19, " Mechanical-Control Diagram - Radiation Monitoring System" 2 R22,. " Mechanical-Control Diagram - Radiation Monitoring System" 3 R13, " Mechanical-Control Diagram - Radiation Monitoring System" 4 R26, " Mechanical-Control Diagram - Radiation Monitoring System" 5 R0, " Mechanical-Control Diagra;n - Radiation Monitoring System" rr. SQN TVA Drawing Series 47W611: 6 R16 " Mechanical Logic Diagraq Ventilation System" 1 R10 " Mechanical Logic Diagram Ventilation System" ss. SQN TVA Drawing Series 47W625: (. -1 R22, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -2 R14, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -3 Rll, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -4 R13, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -5 R14, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -6 R5, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -7 R13, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -8 R18, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -9 R8, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -10 R4, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" -11 R10, " Mechanical-Radiation Sampling System - Auxiliary and Reactor Building" b 1080d - 12/19/86

y; - .L i P PROGR REVISION NUMBER: 1 y Q. g~ PAGE 26 0F'36 rq. 5 APPENDIX A (cont'd) If " Mechanical-Radiation Sampling System - j -12 R7, Auxiliary and Reactor Building" b -13 R6, " Electrical-Radiatior. Sampling System - Auxiliary and Reactor Building" - -14 R9, " Mechanical-Radiation Sampling System - Post ' Accident" -15 R10, " Mechanical-Radiation Sampling System - Post Accident" ';f - -16 R8, " Mechanical-Radiation Sampling System - Post Accident" -17 R8, " Mechanical-Radiation Sampling System - ( Auxiliary and Reactor Building" ( -18 R2, " Mechanical-Radiation Sampling System - ( Auxiliary and Reactor Building" -19 R4, " Mechanical-Radiation Sampling System - k k-Auxiliary and Reactor Building" 4 -20 R3, " Mechanical-Radiation Sampling System - r1, Auxiliary and Reactor Building"

i _ c

-21 R0, " Mechanical-Radiation Sampling System - Post i V Accident"' -52 R1, " Mechanical-Radiation Sampling System - j-Auxiliary and Reactor Building" -53 R1,- " Mechanical-Radiation Sampling System - g Auxiliary and Reactor Building" d -54 R1, " Mechanical-Radiation Sampling System -- Auxiliary and Reactor Building" ]!j -56 R1, " Mechanical-Radiation Sampling System - 4 Auxiliary and Reactor Building" g tt. Letter from L. M. Mills, TVA, to E. Adensam, NRC, No. A27 830304 001 (03/14/83) i' uu. Letter from E. Adensam, NRC; to H. G. Parris, TVA, 1 No. A02 840620 001 (06/15/84) vv. Letter from R. L. Gridley, TVA, to B. Youngblood, NRC, No. L44 860930 805 (09/30/86) ]- 6. WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER 1. APPLY OR CONTROL IN THIS AREA? a. 10CFR50, Domestic Licensing of Production and Utilization Facilities, Section 50.34a, " Design Objectives for Equipment to Control Release of Radioactive Materials in Effluents" b. 10CFR50 Appendix A, General Design Criteria 60, " Control of Releases of Radioactive Materials to the Environment" 1 1080d 12/19/86 x

o 'q TVA EMPLOYEE CONCERNS-REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 27 0F 36 4 . j-[ APPENDIX A (cont'd) '0CFR50 Appendix A, General Design Criterion 6'( " Monitoring 1 c. F . Fuel and Waste Storage" d. 10CFR50, Appendix A, General Design Criteria 64, " Monitoring Radioactivity Releases" 3 e. 10CFR50, Appendix I, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion, as Low as Reasonably Achievable," etc. f. 10CFR20, " Standards for Protection Against Radiation" g. NRC Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from . Light Water Cooled Nuclear Power Plants," R1, (06/74) h. NRC Regulatory Guide 8.8, "Information Relevant to Ensuring e }M that Occupational Radiation Exposures Will Be as Low as Reasonably Achie' able," R3, (06/78) v i. NRC Regulatory Guide 8.10, " Operating Philosophy for Maintaining (Radiation Exposures as Low as Reasonably Ac hievable Nuclear Power Reactors)," R1, (05/77) j. NUREG-0737, Supplement 1, " Clarification of TMI Action Plan Requirements," November, 1980, Section II.F.1, " Additional Accident Monitoring Instrumentation" k. Regulatory Guide 1.97, " Instrumentation to Follow the Course of an Accident," R2, (12/80) 1. FSAR Section 11.4, " Process and Effluent Radiological Monitoring and Sampling System" m. FSAR Section 12.1.4, " Area Monitoring" n. NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report l' and Short Term Recommendation," (July 1979) l-o. NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident," (May 1980) ( p. NUREG-0737, " Clarification of TMI Action Plan Requirements," L (November 1980) l J j 1080d - 12/19/86 N,

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11.(B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 28 0F 36 7. LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER DISCUSSIONS RELATED TO ELEMENT. RFI-594/TVA Transmittal 112. -TVA Transmittal 121 TVA Transmittal 123 Conference October 14, 1986, D. L. Damon, Bechtel, P. B. Nesbitt, R. Cornwall, R. McNight, T. Todd, TVA Phone Conference, D. L. Damon, Bechtel, J. M. Iberford TVA Sequoyah Site, October 14, 1986 Phone Conference, D. L. Damon, Bechtel, R. Cornwall, TVA, October 21, 1986 Phone Conference, D. L. Damon, Bechtel, P. B. Nesbitt, TVA, December 4, 1986. I 1 4 4 1080d - 12/19/86 i

Q M, SNP TABLE 11.6.2-1 LIQUID RADIATION MONITORS Loestion Nnitor Monitor Tile and Assembly Selsele Floor Sacharound Es pec t ed Conc Osentity Type TVA Instr Me. rNontter Close _E l_ 93 (mR /h ) Detector Type Range Scale er Red lawele pens eure d Weste Oleposal 0-85-90-122 t/plent 11 669.0 Aus 1.0 Comme 10-0 to In-I WCl/cc 10 to 80 cpe 1.) a 10-6 croes 6 states U guld Scintillation Come Effluent maltor tesential new 0-St-90-l)). 2/ plant I 690.0 Aus 1.0 t'.a mes 10-6 c. In-l pCl/cc 10 t o 106 cpe Mestisible Croce Coollag Water 116, 160, 161 Sclatillation Conc Liquid %nitor Cnoponent Coollag 0-RE-90-121 3/ plant t 756.0 Aus 1.0 comme 10-6 to 10*I WCl/cc to to 106 stealisible Crees cpe Systee Liguld 1-at-90-123 Sc i nt illa t ion Conc Effluent *toetter 2-RE-90-521 i stese cenerater 1-85-90-120, 2/ plant il 736.0 Aus 1.0 cemen 10-6 go to-1 pC1/cc 10 t o 106 S e to-6* Crose cpe j slowJown Dierherge 128 Sc int illat ion Conc j Sample 2-85-90-120, 2/ plant Monitor 121 i tverorator Con-1-RE-90-170 2/ plant il 690.0 Aus 10.0 Ceems 10-6 g, go-l uC1/cc to to in6 r pe I 80-6 Croce j d one.* e Scintillation Conc j Laguld Effluent

• 88-90-170 j

Munster i j meector Coolant l-88-90-l06 2/ plant i 716.0 Aus 1.0 a:eeme 10*0 t o 10I pCl/cc 10 t o In" c sue Table 11.1.1-2 Croce i Sc int i l la t ion Conc j latJown Liquid 2 -8 t-90-106 Monitor l Stees cenerator I -R E-90-l 2 6 1/ plan' il 716.0 Aue 1.0 cases 10*6 g,30-1 pCl/cc t o t o In" c pe 10-6 Crose 4 Sc int illa t ion Conc Blodewn Liquid l Montter

• If reverse nosoele concentrates are belns discharged, the concentration will be shout ten flees wJlue endicated.

t i i 4 i

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 29 0F 36 ATTACHMENT NO. 1 SQN FSAR a. . Table 11.4.2-1 Liquid Radiation Monitors l l l s I i i ei !i t i 1080d - 12/19/86 ,1

TVA EMPLOYEE CONCERNS-REPORT NUMBER: 229.11 (8) SPECIAL PROGRAM REVISION NUMBER: 1 ~ PAGE 30 0F 36 . ATTACHMENT N0. 2 SQN FSAR a. Table 11.4.2-2 Gaseous Rndiation Monitors [ I s Qt 1080d.- 12/19/86

e e 9 e .e bg. e. .e e - e e. s .l..e r _ c s,fe. 0 _. .e.s.s s. t e .c e q g e - r J g 'a.g c. ja e L; b 6 - e. Oh' e 6 s.e. s C 1 d . e Lt > 9 e up g

• ".g.

m 3 C C C C e. y E .c. .e .5 W u er og .3 )= 6 e e a a b s u y 27 2 2 J J 1 1 I t f. f f_ E E s b. 6 4. w s 2 2 2 2 t 2 .C. C .C* C. _C .C. .C.

== .C. C e A .e. .e .e. .e. .e. .e. C C .C. _C .C. _C .C. .C. .C. e b b W b b. b. b. b b t b b e e w b w b r W W b b U L' G V e a L 1 3 3 4 4 e - t W af

• S e9 ef 4

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m a- : - r. p-~ .i * = Sh? TABt.E 11.6.2 2 (Continue.1) CAstoirS RADI ATION MONITORS %heet ) tecetton

• onttor Bern round Espected Cone Osentity Monitor Tlle end assembly Seleele Floor a

Type TV4 Inste too. 'ysent i t y close El g (en/h) lieter. tar Tyge Range Scale or s d lieele Mea sure d Puel Ponte 0-RE-90-102 2/ plant 734.0 Aus CM Tubes 10*I to 10' mR/h 10*I to lne en/h 10-3 mR/h Cross ("sne Redletion mnitore 0-at-90-103 6 Contelnment Purge 8-at-90-lio 4/plent i 690.0 Aus 10.0 sete i a 10-4 to 10 to 10 cpe (See test) Craes 0 M r Eshouet 1-RE-90-111 Scintillation ) z 10 i<l/cc Monitore cee 2-at.90-110 2-eF-90-13I l I 9

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 31 0F 36 ATTACHMENT NO. 3 SQN DESIGN CRITERIA, SQN-DC-V-9.0 " Radiation Monitoring System" a. Table 9.0-1 Monitor Description

i. :

th' t l b; i [ 1080d - 12/19/86 i

m (7) .\\ r RADIATION PCHITORING SYSTEM SQN-DC-V-9.0 TABLE 9.0-1 PONITOR DESCRIFIION Honitor Function Instrtunent Channel Monitoring Control Notes Monitor Ntznber Qty Detector Type I. Gaseous Effluent Honitors Condenser Vacuum Pump Exhaust vent Normal Range 1-RE-90-119 2/ Plant Offline Beta Scint. Yes No 7 High Range 1-RE-90-99 2/Plar.t Offline Beta Scint. Yes No 7 Accident Range (Interim) 1-RE-90-255&256 2/ Plant Online G-M Tube & Ion Ctunbr. Yes No 7 Accident Range 1-RE-90-404 2/ Plant Offline G-M Tubes Yes No 7 Shield Building Vent Normal Range Particulate 1-RE-90-100A 2/ Plant Offline Filter & Beta Scint. Yes No 5,7 Noble Gas 1-RE-90-1003 2/ Plant Offline Beta Scint. Yes No 5,7 Iodine 1-RE-90-1000 2/ Plant Offline Filter &G-M Tube Yes. No 5,7 Particulate, Noble Gas, Iodine 1-RE-90-400 2/ Plant Offline Composite Det. Yes No 7 Accident Range (Interim) 1-RE-90-2606261 2/ Plant Online G-M Tube & Ion Clusbr. Yes No 7 Accident Range 1-RE-90-401 2/ Plant Offline G-M Tubes Yes No 7 Auxiliary Building Vent Particulate 0-RE-90-101A 1/ Plant Offline Filter & Beta Scint. Yes Yes 5,7 Noble Gas 0-RE-90-101B 1/ Plant Offline Beta Scint. Yes Yes 5,7 Iodine 0-RE-90-101C 1/ Plant Offline Filter & G-M Tube Yes Yes 5,7 Contairunent Bldg Purge Air Exhaust 1-RE-90-130 2/ Plant Offline Beta Scint. Yes Yes 7 l-RE-90-131 2/ Plant Offline Beta Scint,. Yes Yes 7 E86188.01,

m ma.,a 3

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s 9)N-DC-V-9.0 k.s1ATION PONITLEING SYSTEM TABIE 9.0-1 (Continued) t0NITOR DESCRIPTION Monitor Instrtsnent Channel Detector Function Monitor Ntsaber Qty Type Monitoring Control Notes 11. Liquid Ef fluent Monitors Plant Liquid Discharge 0-RE-90-211 1/ Plant Offline Casuna Scint. Yes No 8 Station Sump Discharge 0-P2-90-212 1/ Plant Offline Gamma Scint. Yes No 8 Reactor Coolant Drain 1-RE-90-277 2/ Plant Online G-M Tube Yes Yes Tank Discharge 1-RE-90-278 2/ Plant Online G-M Tube Yes Yes Contairement Blds Floor and Eqpt. 1-RE-90-275 2/ Plant Online G-M Tube Yes Yes Drain Stamp Discharge 1-RE-90-276 2/ Plant Online G-M Tube Yes Yes III. Process Monitors Main Control Room Air Intake Normal Path 0-RE-90-125 1/ Plant Offline Beta Scint. Yes Yes 8 0-RE-90-126 1/ Plant Offline Beta Scint. Yes Yes 8 Emergency Fath 0-RE-90-205 1/ Plant Offline Beta Scint. Yes No 8 0-RE-90-206 1/ Plant Offline Beta Scint. Yes No 8 Fuel Pool Air Space 0-RE-90-102 1/ Plant Area G-M Tube Yes Yes 8 O-RE-90-103 1/ Plant Area G-M Tube Yes Yes 8 Steam Generator Blowdown Lines Casson Header 1-RE-90-120&l21 2/ Plant Offline Casma Scint. Yes Yes 7 Individual Sample Lines 1-RE-90-124 2/ Plant Offline Gemma Scint.' Yes No 7 Residual Heat Removal Lines 1-RE-90-290,291 2/ Plant Online G-M Tube & Ion Chabr. Yes No 7 l-RE-90-292,293 2/ Plant Online G-M Tube & Ion Chabr. Yes No-7 E86188.01.

1 [ 9 'P RADIATION PONITGlING SYSTEM SQN-0C-V-9.0 TAB 12 9.0-1 (Continued) MONITOR DESCRIPTION tbnitor Inst rtusent Channel Detector Punction Monitor Ntsaber Qty Type Monitoring Cootrol Notes IV. Airborne Monitors Main Control Rocus 0-RE-90-105 1/ Plant Part Filter & Beta Scint. Yes No 8 Contairnent Bldg. Upper Ccuspartment Normal Range Particulate 1-RE-90-Il2A 2/ Plant Offline Filter & Beta Scint. Yes Yes 5,7 Noble Gas 1-RE-90-Il2B 2/ Plant Offline Beta Scint. Yes Yes 5,7 Iodine 1-RE-90-Il2C 2/ Plant Offline Filter &G-M Ibbe Yes No 5,7 Accident Range 1-RE-90-271 2/ Plant Area Ion Chamber Yes No 7 l-RE-90-272 2/ Plant Area Ion Chamber Yes No 7 Contairment Bldg. Imer Caspartment Normal Range Particulate 1-RE-90-106A 2/ Plant Offline Filter & Beta Scint. Yes Yes 5,7 Noble Gas 1-RE-90-106B 2/ Plant Offline Beta Scint. Yes Yes 5,7 Iodine 1-RE-90-106C 2/ Plant Offline Filter &G-M Tube Yes No 5,7 Accident Range 1-RE-90-273 2/ Plant Area Ion Chamber Yes No 7 l-RE-90-274 2/ Plant Area Ion Chamber Yes No 7 Outside Containment Building Personnel Hatch 1-RE-90-2 2/ Plant Area G-M Tube Yes No 7 i V. Area Monitors Main Control Rocus O-RE-90-135 1/ Plant Area G-M Tube Yes No 8 Post Accident Sample Room 1-RE-90-280 2/ Plant Area G-M Tube Yes No 7 E86188.01 _

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 32 0F 36 ATTACHMENT NO. 4 SQN DESIGN CRITERIA, SQN-DC-V-9.0 " Radiation Monitoring System" a. Table 9.0-2 Monitor Safety Requirements l' 9 1080d - 12/19/86

w ,. - ~.. J [ ATION MNITORINC 9YSTEM SQN-DC-V-9.0 TABIE 9.0-2 NONITOR SAFETY REQUIREterrS Instrument Safety Class Seismic Elect Vital Monitor Nunber Mech Elec Category Separation Power Redundant Notes I. Caseous Ef fluent Nonitors Cordenser Vacuust Puup Exhaust Vent Normal Rcnge 1-RE-90-Il9 H Note 3 None None Note 2 No 9 High Range 1-RE-90-99 H Note 3 None None Note 2 No 9 Accident Range (Interim) 1-RE-90-255&256 NA Note 3 None None Note 2 No 1 Accident Range 1-RE-90-404 H Note 3 None None Note 2 No 9 Shield Building Vent Normal Range Particulate 1-RE-90-100A B None Note 11 None No No 5,9 Noble Ces 1-RE-90-100B B None Note 11 None Pb No 5,9 Iodine 1-RE-90-100C B None Note 11 None No No 5,9 Particulate, Noble Ces, Iodire 1-RE-90-400 B Note 3 None None Note 2 No 9 Accident Range (Interim) 1-RE-90-260&261 NA tbte 3 Note 11 None Note 2 No 1 Accident Range 1-RE-90-401 B Note 3 None None Note 2 No 9 Acxiliary Buildirg Vent Particulate 0-RE-90-101 A S lE I TRN A/TRN B Yes No 4,5,9 Noble cas 0-RE-90-101B S lE I 1RN A/TRN B Tes No 4,5,9 Iodine 0-RE-90-101C S lE I TRN A/ TEN B Tes No 4,5,9 Contairunent Bldg Purge Air Exhaust 0-RE-90-130/131 S IE I TRN A/TRN B Tes Yes 9 E86188.01 : } O.

$h r-RADIATION MMITULING SYSTEM SQN-DC-V-9.0 TABIE 9.0-2 (Continued) MONITOR SAFEIT REQUIRE!ENTS Instrtsnent Safety Class Seismic Elect Vital Monitor Ntsnber Mech Elec Category Separation, Power Redundant Notet II. Liquid Effluent Monitors Plant Liquid Discharge 0-RE-90-211 H Hone None None No No 9 Station stasp Discharge 0-RE-90-212 H Hone None None No No 9 Reactor Coolant Drain Tank Disch. 1-RE-90-277/278 R 1E I TRN B/TRN A Yes Yes 1 Containment 5143 Ploor and Eqpt Drain Sissp Discharge 1-RE-90-275/276 m 1E I TRN B/ M A Yes Yes 1 III. Process Monitors Main Control Room Air Intake Normal Path 0-RE-90-125/126 C IE I TEN A/ M B Yes Yes 9 Emergency Fath 0-RE-90-205/206 C IE I TEM A/ M B Yes No 9 Fuel Pool Air Space 0-RE-90-102/103 m 1E I TEN A/ TIRE B Yes Yes 1 Steam Generator Blowdown Lines Canson Header 1-RE-90-120&l21 H None None None No No 9 Ichiivi& sal Sasple Lines 1-RE-90-124 G,B None Note 11 Nooe No No 6 Residual Heat Resoval Lines 1-RE-90-290& NA 1E I TEN A/ TEN B Yes No 1 291/292&293 E86188.01 - s

a e n DTATTON NNITORING SY9TDi SqN-DC-V-9,0 TABIE 9.0-2 (Contirmed) MONI1DR SAFETY REQUIRDB S ~ Instrument Safety Class Seimnic Elect Vital &ch Elec Category Separation Power Redundant Notes Nnitor Ntsiber IV. Airborne k nitors Mein Control Roosi 0-RE-90-105 NA None I None No No 1 Conceirusent Blds Upper Compartment Norumm1 11ange Particulate 1-RE-90-Il2A B IE I Tief B Yes Yes 5,9,10 Noble Gas 1-RE-90-Il2B B IE I 1RN B Yes Yes 5,9,10 Iodine 1-RE-90-112C B IE I 1RN B Yes No 5,9 Accident Range 1-RE-90-271/272 NA lE I T10t A/ TEN B Yes Yes 1 Contairement Bldg lower Compartment Normal Range Particulate 1-RE-90-106A B IE I TRN A Yes Yes 5,9,10 Noble ces 1-RE-90-106B B IE I 1RN A Yes Yes 5,9,10 Iodine 1-RE-90-106C B IE I 1RN A Yes No 5,9 Accident Range 1-RE @ -273/274 NA lE I 1156 A/1146 B Yes Yes 1 Outside Cortainment Buildits Personnel htch 1-RE-90-2 NA kne Note 11 Mone No No 1 Y. Area Monitors Main Cortrol bom 0-RE-90-135 NA kne I None No No 1 Poet Accident Sasple Room 1-RE-90-280 NA None Note 11 None No No 1 E86185.01 _ m. .G.

i TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) ) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 33 0F 36 ATTACHMENT NO. 5 SNUPPS FSAR a. Table 11.5-1 Liquid Process Radioactivity Monitors b. Table 11.5-2 Liquid Effluent Radioactivity Monitors c. Table 11.5-3 Airborne Process Radioactivity Monitors d. Table 11.5-4 Airborne Effluent Radioactivity Monitors e. Table 12.3-2 Area Radiation Monitors t C i 1080d - 12/19/86 1

y. a.) m).' ~

• )

L SMUFFS d TABLE 11.5-1 LIQUID PROCESS RADIOACTIVITY MOW!1tNts Sample Control-Alert N1 Flow Monitor Monitor Type Range IOC (1) ling Alarm - Alarm Rate Control Number Description Econtinuwel Detection (pci/cc} (pcifec) Isotope (pci/ce) (pci/ce) ( gpa ), Function 0-EC-pt-g ev aant Liquid Nat (TI) 10*' to 10-s 1 a 10** Co-137 1 a 10**(3) 1 a 10**(4) 1-5 Isolates 0-EG-RE-te cooling gasone air vents water scintilla-on component monitor tion cooling water surge tanks on Mi alarme 0-SJ-RE-2 Steam gener-Liquid (2) Wal (T1) 10*' to 10** I a 10** Co-137 1 a 10**(3) I a 10**(4) 1-5 Closes stor liquid gamma blowdown radioactiv-scintilla-isolation ity monitor tion valves on Mi alarm 0-BM-RE-25 Steen gener-Liquid (2) Net (71) 10*' to 10*8 1 a 10-e Co-137 1 a 10*8(3) 1 a 10**(4) 1-5 Closee eter blowdown gamma blowdown processing scintilla-isolation system monitor tion velve on Ni alarme 0-EA-RE-4A Service water Liquid Nat (71) 10*' to 10-s 1 a 10** Co-137 1 a 10-s(3) 1 a 20**(4) 1-5 Alerne 0-EA-RE-45 monitor gamma sesntille-tion o !!E-RE-16 Baron recy-Liguld (2) Wat (71) 10*' to 10*8 1 a 10** Co-137 1 a 10**(5) 1 a 10**l6) 15 Alert alarm p cle eyeten gamma diverte distillate scintilla-flow to re-monitor tion cycle hold-up tant 10*sg73 g gag ,3-1 Alarme 0-SJ-RE-01 Chemical and Liquid Nat (TI) 10** to 1 NA volume con-gamma trol system .scinti!!a-1stdown tion monitor 0-EF-RE-35 Essential ser-Liquid Nat (T1) 10*' to 10** 1 a 10-e,Co-137 1 a 10*8(3) 1 a 10**(4) 1-5 Alarme 0-EF-RE-36 vice water gamme system monitor scintilla. tion 0-TB-RE-50 Ana111ery Liquid (2) Not (71) 10*' to 10*8 1 a 10** Co-137 1 a 10-s(3) 1 a 10**(4) 15 Hi alarm teolates steem system geoma condensate scintilla-aum111ery recovery tion steam monitor supply to redweste building and tripe aus111ery steam con. densate transfer purps 9 Rev. 15 6/94

} + e SWUFFS TABLE 11.5 1 (Sheet 25 LIQUID PROCESS RADIOACTlvlTY 880881700$ sasyle control. Alert Ni Flow IIonitor Monitor Type penge PSC til Inng Alarm Alarm pote Centrol. WJacer Descrip ion teontinuous) Detection (yCa/ce) tyCi/cci footope tyCa/ce) (pCn/gg) g Function 0-MC-SE.1 padwaste so. Liguad Ital (?!) 0.1 - 10'rsht 0.1 r/hr NA NA las een ten o-MC-pt-2 Iadifacatson gasune syntee scantilla-monator tson s (1) IOC - minimum detectable concentretien. When an operation. 123 833 One orden of eagnatode above see to avoid sFurious alarme and to indicate the lestege of radioactivity into en otherwise nonradaoactave system. (4) Two orders of regnatade above feC to andscate significant Inleekage of radioactivity. (5) only water cleaner then this will be sent to the reactor makeup water storage tank. f6) Magh actawity may indacate evaporator operating problem. (75 Migh activsty may andicate a ciud burst or todane spiting. (S) Migh actavity may andacate a cred burst, iodine spiking, or failed fuel. Laboratory analysee will be performed to determine cause. 6 f 4 9/00

1 Q Q p v e G ^ SNUPPS TABLE 11.5-2 LIQUID EFFLUENT RADIOACTIVITY MONITORS Sample control-Alert Hi Flow Monitor l Monitor Type Ran9e MDC (1) ling Alarm Alarm Rate control I Number Description (continuous) Detection (pC1/cc) (pci/cc) Isotope (pci/cc) . (uci/ce) (qpe) Function 0-HF-RE-45 Secondary Liquid (4) Na! (TI) 10~7 to 10~8 1 x 10 s Cs-137 (3) (2) 1-5 Closes discharge liquid waste gamma valves on system scintilla-high alara monitor tion 0-HB-RE-18 Liquid rr.d-Liquid (4) Nat (TI) 10~' to 10~8 1 x 10 s Cs-137 (3) (2) 1-5 Closes discharge waste dis-gasuna valve on charge scintilla-high alarm monitor tion 0-LE-RE-59 Turbine Liquid (5) Na! (TI) 10 to 10~8 1 x 10 s Cs-137 (3) (2) 1-5 Closes discharge building gamma valve on drain scintilla-high alarm monitor tion 0-BR-RE-52 Steam gener-Liquid (4) NaI (TI) 10~F to 10 2 g x go s Cs-137 (3) (2) 1-5 Closes dis-charge and ator blow-gasma blowdown down discharge scintilla-isolation monitor tion valves on high alarm MDC = minimum detectable concentration. l (1) High alarm is set to ensure that Technical Specification limits (the 10 CFR 20 (2) general population MFCs for the controlling isotope at the boundary of the restricted area) are not exceeded and to initiate isolation before the limit can be exceeded. Alert alarm is set one order of magnitude belota the Technical Specification limits to alert (3) operators of alert radioactivity levels. The monitor is to prevent inadvertent discharge Normally, all of this 1,iquid will be recycled. (4) valve opening and to ensure that any releases that might become necessary are within limits. In accordance with the Technical Specifications, batch analyses will be performed before any releases are made. (5) Normally, not radioactive since potentially radioactive drains are segregated from this and recycled. 6 e Rev. 1 9/80

FLX-m ;m. 3. 4 Omr-*_;a:h e ~w.%-w ww - w_ QY "h sNuPrs TABLE 11.5-3 AIRBORNE PROCESS RAD 10ACTIVITT MON 110R$ Total Minimuse control-Alert Ri Venti. Dequired Monitor Type Range MDC (1) lang Alarm Alarm lation senettivity Control Monitor (continuomel fyC1/cc) (pci/cc) Rectore (yci/cc) (yC1/ce] Flow (cfm) (yC1/ce) Function 0-CT-RE-31 Particulate (3) 10*88 to 10*' I a 10*8' Co-137 I a 10**(8) I a 10*'(7) 420.000 1 a 10*'(7) leolates con. 0-CT-at-32 tainment purge. Containment todine (4) 10 es to 10** 1 a 10 se 3 333 9 a 10 e(s) 9 a 10 e(7) 420.000 9 a 10 s(7) de-energises atmosphere purge fans on monitore Caeeene (3) 10*' to 10** 2 a 10*' Er-05 1 a 10 s(8) 1 a 10**8?) 420.000 1 a 10**(7) high gaseous activity via the FSFILS (see section 7.3). 0-CT-RE-22 Ferticulate (3) 10*88 to 10*' 1 a 10*88 Co-137 1 a 10 e(8) 1 a 10*'(7) 20.000/4000 1 a 10*'(7) loolstee con-l O-CT-RE-33 tainment purge,l Containment lodine (4) 10* s to 10** I a 10*8' 1-131 9 a 10**(S) 9 a 10 e(7) 20.000/4000 9 a 10*'(7) de-energises purge system purge fans on monsters Caseous (3) 10*' to 10*' 2 a 10*' Kr-05 1 a 10~8(8) 1 a 10**(7) 20.000/4000 1 a 10**(7) high gaseone activity via the E3FAS (see Section F.3) 0-CT-RE-59 Casma (5) I to 10' rede 1 rad MA NA NA NA NA NA o-CT-pE-60 T~ W Conta arJeent htgh activity monitore 0-CE-RE-92 Caseous 10*' to 10*' 2 a 10*' Kr-85 2 a 10 *(9) 2 a 10's(10) 1000 NA Closee blow-Condenser (continuous) down teolation air die-(3). (6) valve on charge ni alarme anonster Ferticulate (lab analyele) (s) todine (lab analyels) (6) 0-OG-RE-27 Ferticulate (3) 10'es to 10*' 1 a 10 se Co.137 1 a 10**(8) 1 a 10*'(7) 20.000 1 a 10*'(7) Initiates o-oc-az-23 emitch to feel Fuel build-lodine (4) 10*88 to 10** 1 a 10*88 1-131 9 a 10**(S) 9 a 10*8(7) 20.000 9 a 10**(7) building ing exhaust emergency ven. monitore(2) Caseous (3) 10*' to 10*8 2 a 10*' Er-85 1 a 10*8(0) 1 a 10**(7) 20.000 1 a 10**(7) tilation on high gaseous activity via the ESTAS (see Section 7.3) 0-Cx-et-04 Particulate (3) 10 se to 0** 1g 10 se Co-137 1 a 10 e(S) 1 a 10*'(7) 1950 1 a 10*'(7) Initiates O-Ca-RE-05 owitch to con-Control lodine (4) 10*88 to 10*e 1 a 10*8* I-131 9 a 10**(S) 9 a 10 e(7) 1950 9 a 10 e(7) trol room emergency wen-room air supply caseone (3) 10*' to 10* 2 a 10*' Mr-85 1 a 10**(8) 1 a 10**(7) 1950 1 a 10**(7) tilation on monttore high gaseous activity via the ESFAS (see - Section 7.3) sample flow for each channel le 3 cfm (I) FOC

• minimuss detectacle concentration.

(2) tfhen fuel is in the building. (3) Beta scintillation detector. (4) Camma scintillation detector. ~ (5) Comme sensitive son chamber. (6) tihen in operation. (7) 10 MFC. (8) M*C (9) One order of magnitude above DOC to avoid spurious alarme and to indicate primary to secondary leakage. (10) 1%o orders of magnitude above DOC to indicate significant inleekage of radioactivity. ,,,, 9 S/92

A4. we. s m_e ~y . ; wm ,+ r =. g o. SemFFS TABt.E II.5-4 AID 90RNE EFFLL'ENT RADICACTIVITY B018170R5 Total minimum Control-Alest 18 1 venti-Oilm-Seguired seenitoc TFpe penge POC ( 3 ) ling Alarm Atare lation tion Senettivity Centrol ngna g (contaneous) (yci/ce) [yct/ce) gotope tyCn/ce) (yC /cc) Flow tefe) Factor toc 1/cc) Function 0-CT-pt-21A Particulate (2) 10*'8 to 10*' I a ig*ee co-137 (e) (1) 64.000 (4) (5) Alarmo Flent most went ledine (3) 10*s' to 10** 1 a 10*** l-131 (0) (7) 64.000 (4) (5) (6) maastor o-CT-DE-218 Ceeeone (2) 10*' to 10' 2 a 10*' xe-133 (s) (7) 64,000 (4) (5) Flant anst vent monator 0-CH-St-104 Particulate (2) 10'er to 10 ' I a 10* Co-137 (S) (?) 12.000 (4) (5) Ni elarm tootetes the peJueste baaldang lodine (3) 10**' to 10** I a 10*'* 1 131 (s) (7) 12.000 (4) (5) weste ges decay tank discharge enhaeet line moeistor 0-Cet-DE-1CS Caseous (2) 10*' to 10' 2 a 30*' Ne-133 (0) (7) 12.000 (4) (5) pedweste tmalding enneust monster o-CI.-RE-40 Aeenlaery Ferticulate (3) 10 *'8 to 10 ' 1 a 10*** Cs-137 (9) (7) 20.000 (4) (7) Alarus ventilation eshaust monator 0-CE-RE-41 Access Ferticulate (3) 10*'8 te IO*' I a 10* Co-137 (8) (1) 1950 (4) (7) Alarus control aree wentiletaon eehaust monitor Sample flow for eacta channel is 3 cfm (1) sec e minimum detectobte concentration. (2p mete sciatallation detector. Campa scinttilation detector. (33 calutionfactoraventflowrateinm/seef(annualeverage). 3 (4) Manteum required sensitivity of monitor its s*8"e/cc at meatmum alloweble annual average concentration (5) of contro11ang tootope at monitor which wall reemit $n annual everage Appendia 1 dose at the site boundary a population MFC for controlling where the bioaccumulation factor le 1 for I I tootope " T55 " bio ccu ulation rector ' diiutaan f actor l notte gases and 1.000 for todines and particulates. See offeite Dose Calculation Manual. (6) Creb eas91ee will be snelyzed an the laboratory. and low todine concentrations wit! be calculated, using paevsously estabitehed ration. Migte stare le set to ensure that technical specification limite (the 10 CFR 20 general (7) populetten nFCs for the contratting sootopes at the boundary of the restricted areal are not exceeded. Alert alarm to set to etert operatore to that average concentration which. if maintained for (8) a full year, would result an the le CFR 50 Appendas I annual dose guidelines being reached. See offsate Cose Calculation Manual. O O ^ .ew., 5/s2

w- - ~ a - ~um m wn_. m a... <~ Suures Tant.E 12. 3-2 AREA RADIATION NON!10RS Radiation Range Hi Alarm Mi-Ni Alarm Instrument Number Incetion zone (oren/he) (oren/hr3 teren/hr) 0.1-10l 2.5 (1) 15 (2) 0-SD-RE-1 Radweste Building Corridor. Basement 8 0-SD-RE-2 Radweste Building Corridor, Basement B 0.1 - 10 L5 W 15 (2) 4 0-SD-RE-3 Radweste Building Corridor, Basement 8 0.1 - 10 2.5 (1) 15 (2) 4 0-SD-RE-4 Radweste Rutiding Corridor, Ground rioor 8 0.1 - 10 2.5 (1) 15 (2) 4 O SD-RE-5 Radweste Building Corridor, Ground rioor 8 0.1 - 10 2.5 W 15 (2) 4 0-SD-RE-6 Solid Radwaste Area B 0.1 - 10 2.5 W 15 W 4 8 0.1 10 2.5 W 15 (2) 0-SD-RE-7 Truck Space 4 B 0.1 - 10 2.5 (1) 15 W 0-SD-RE-8 Sample Laboratory 4 0-SD-RE-9 RW Blog valve Room Corridor C 0.1 - 10 15 (1) 100 (2) 4 0-SD-RE-10 RW 816g Valve Room Corridor C 0.1 - 10, 15 W 100 (2) O-SD-RE-11 RW Bldg HVAC ritter Unit 8 0.1 10 2.5 W 15 W 4 B O.I - 10 2.5 (I) 15 (2) 0-SD-RE 12 Aus 81dg Corridor Basement 4 B 0.1 - 10, 2.5 (1) 15 (2) O-SD-RE-13 Aus Bldg Corr 1Jor Basement B 0.1 - 10 2.5 (1) 15 (2) 0-SD-RE-14 Aus Blog Corridor Basement 4 n 0.1 - 10, 2.5 W 15 (2) 0-SD-RE-15 Aus Bldg Corridor Basement 0-SD-RE-15 Aus 81dg Corridor Basement B 0.1 - 10 2.5 (1) 15 (2) 4 8 0.1 - 10, 2.5 W 15 W 0-SD-RE-17 Fipe Tunnet & Personnel Access 0-SD-RE-18 Aus Bldg Ground Floor Corridor 8 0.1 - 10 2.5 (1) 15 (2) 4 O-SD-RE-19 Aus Bldg Ground Floor Corridor 8 0.1 - 10 2.5 W 15 W 4 0-SD-RE-20 Aus 81dg valve Room Corridor Ground Floor C 0.1 - 10 15 (1) 100 (2) 4 0-SD-RE-21 Aus 81dg valve Room Corridor Ground rioor C 0.1 - 10 15 (1) 100 (2) 4 0-SD-RE-22 Aus Bldg Corridor Ground Floor 8 0.1 - 10 2.5 (1) 15 (2) 4 0-SD-RE-23 Aus Blog Corridor Ground Floor B 0.1 - 10, 2.5 W 15 W C 0.1 - 10, 15 (1) 100 (2) 0-SD-RE-24 RC Sample Room 0-SD-RE-25 ritter Unit Aus Blog A 0.1 - 10, 0.5 W 2.5 (2) 0-SD-RE-26 RNR Nest Eschanger Outside 8 0.1 - 10, 2.5 W 15 m O-SD-RE-27 Ctat Purge rilter Unit C O.1 - 10 15 W IM W 4 8 0.1 - 10, 2.5 W 15 W 0-SD-RE-28 Personnel Natch 8 0.1 - 10 2.5 (1) 15 (2) O-SD-RE-29 Not Machine Shop 4 O-SD-RE-30 Mot Instrument Shop 8 0.1 - 10 2.5 (1) 15 (29 4 8 0.1 - 10 2.5 W 15 W 4 O-SD-RE-31 Hot taboratory 0-50-RE-32 Control 81dg Corridor 8 0.1 - 10 2.5 (1) 15 (2) 4 A 0.1 - 10 0.5 (1) 2.5 (2) 0-SD-RE-33 Control Room 4 0-SD-RE-34 Cask Handling Area (3) B 0.1 - 10 2.5 (1) 15 (2) 4 0-SD-RE-35 New ruel Storage Area (3) 8 0.1 - 10 2.5 (Il 15 (2) 0-SD-RE-35 New ruel Storage Area (3) 8 0.t - 10, 2.5 (1) 15 (2) 0.1 - 10, 2.5 W 15 W 0-SD-RE-37 Spent Fuel Fool Area (3) B 4 0-SD-RE-30 Spent ruel Pool Area (3) B 0.1 - 10 2.5 W 15 W 4 E O.1 - 10 I M (4) IM N i O-SD-RE-39 3eal Table Area 4 O-SD-RE-40 Personnel Access Hatch Area E 0.1 - 10 I W (4) IM W 4 O-SD-RE-41 Containment Building E O.1 - 10, I M (4) IM (H 0-SD-RE-42 Containment Building E 0.1 - 10 1000 (4) 10000 (5) 0-50-RE-43 Technical Support Center A 0.1 - 104 0.5 (1) 2.5 (2) 8 0.5 (1) 2.5 (2) O-SD-RE-44 t>ergency offsite racility A 0.1 - 10 1."0-10) 5 - t" iOOO i. 20000 (ti Pass Samplin'Br"adg"e Crane (6) E 0-SD-RE-47 W N/A manipulator Portable i (1) Rich alarm set for eastmum radiation level for the radiation zone for that area. (2) High-high alern set for the pasimum radiation level for the radiation zone above the one for that area. i These monitors serve as criticality monitors. ( 3) Righ alarm based on highest espected radiation level for the area during full power operation. is) Righ-high alarm set one order of magnitude above high alarm to indicate extremely high radiation level. (5) The monitor will be positioned on the (6) This is a portable monitor providing a local alarm and readout. bridge crane only during plant shutdown when fuel handling activitien are occurrino. This monitor will pey 35 be replaced by a permanent monitor which will be installed at Callaway during the first refueling outage. 5/84 (7) High alarm is established for the protection of operators on the bridge crane and is set at 15 mrrm/hr i above background radiation levels, 1 4 v

TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 34 0F 36 ATTACHMENT NO. 6 Palo Verde FSAR a. Table 11.5-1 Continuous Process and Effluent Radiation Monitoring NOTE: Area Monitors are included in this Table 11.5-1 for PVNGS r I i G I' 1080d - 12/19/86

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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 PAGE 35 0F 36 ATTACPNENT NO. 7 San Onofre 2 & 3 FSAR i a. Table 11.5-1 Continuous Process and Effluent Radiation Monitoring b. Table 12.3-2 Area Radiation Monitor Locations l l i n f.$3 3$, b$ I a ,1 n -r .. t 1080d - 12/19/86

,,a y augun zu.us,mu a m _,,m m _. .,,m 6< s. = a c, v - Table 11e5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION-MONITORING (Sheet 1) Espected 41er=II) Actietty rollbration Reene Ceneenttejlens Setentet Aufnmatte Aetlane Sampler / q jar f.nc e t t en Quentity sempler Type Detector Type Mesenred lentope (wCt/cm ) (vC1/e= 1 (pC1/c=Il pnwer supply inittoted 3 Weste see i Off!!ne/ges tene range: Urceo ft F r - R *. In'".le*I l>tnfb) 6 10 Inseramentetinn Alarm ente oc heie header (WCM) it et tat ille. m mttar tion (2/191-7Aleg f isiev e ll.)-l) Ittah range: Cros e 6 fr-85 10*3-102 I.s gr.ng 4.0 instenmentation Alarm and inftlete' Kr-85 ac bus einente of weste see s selettete. discherer valve t i on heatretiretten 2 Offline/ v setatille-Crose e Co 117 10"*-10*I 2.410-6 Sa10' Ins t riment e t i nn Aterm and etepe linu Co.337 Co-137 ee bue e.*r discherse (1 per liguld tien IN$D) Monitor Un{t) (28T.7817 and O jet-7817 fin-are 10.4-2 oh l) C E 2:10** Inst riement e t t en Alarm only Camponent 2 Offline/ vocintille-Croge y co.117 10-6. I n* I tJen hC Co-III se bwe [ enetica weter (1 per itquid tion g3, e-(CCW) eent ter unit) at fl La (7RT.7819 and f* h I ler-7439: lisure 9.2 1 4 sh 2) ett medweste 1 Offline/ Y setatille-Crane y Co-117 10-6.g o-t 7.2 10 2:10~ fnetroentatten A1sta and Intelete 2 discherme line liquid tien Co-137,3 Co-137 oc bue elcopre of redweet' On g diecherme valve 'iC t's

f. Oslo M

"h (p hi.) monit or Co-134 (7/leT-7All; 4.4s10'II-131 ilaure II.2-t sh 7, w ~ [ Turbine plant 2 Offitne/ vocintille. CroseY Co-137 10-6-10-1 Isto 2:10 ' instrumentatten Aler= end divert 1-131 et bus discherme en th' t's eres e4mp (I per liguld tien redweet c nump = (TpAS) montter unit) (?RT 7R75 en.f ti) h 337-7878

l; g fiene, 9.1-7 et, 7,

q t** A3 See e cc t i nn 1. 7 fo r i nc i ne t en o f P4 t n m.pher e hy re f erenc e,

c. The Inie rence sonnitnr te need te determine firer taridence w> of steem menerater tuhe leskene in enninnet ten with felled 2*. Of e. CI b. l>pt te lese then a.latema detec tehle. Init tel espected enneent rollane are le** then feel. Ifence C. Monitor utilises tambined ledine-particulate detector. The eterm setpoint to beoed on 1-131 mtalasse detectable far that maniter, me d. In cerec t ed enneentrat tune entumn. the firer number refere in rendir tems f. Re-313 le the ra t e bret t en lenter, for 1-138

== O 4ere e Cet rolesse to la progrege/second numf.er retterfs en CR'; g. Nr-89 le the celthrottan 1*ntere In' Ie*Ill-h h. Contelnment purge tecletten Sneludeo Ierge TelWee purre g3 () denrherge. 1seletion and =tal-pwrse tooletten. .4 g M-1. Actuel.elere setent ate estohltehad k' t * 'er%n tral ':pec tit eet scas. h e i 1

n-. O~ Q l O q Table 11.5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION MONITORING (Sheet 2) Espected

• Alere Ill Activity Celebretion pense Autometic Actions 1.oretion Quentity Sempler Type Detector Type

'tesaured Isotere (pCl/c=y) Concentregione Setroing) sempler/'toger (pC1/cm ) (pct /r= Power supply Inittsted 1.5:10 Instrumentation Alere end divert a e i Offline/ y erintelle-Crosa y Co-837 10'0-10'I IJED Ce-137 oc bus flow to miscel-rendensate liquid tien loneous westre return (RCA) tank sonnter 2/.1RT 7812 figure II.2-l sh 1) I8I 10'0-10 Ss10Ke-133 1:10'3 Vital oc buses Alere and inittete Containment 4 Ces p scintelle. Cross p Kr-55 Ic-13) cont e tsveeygparte sieharpe (CA) (2 per tion leolatien monitor unit) t (2RT-7A04-1, ,g ,g ,g ,q 3RT-FA04-l, Meving p scintille-Cross p Cl-36 & 10 -10 3.9 10 OsIO Vital se buses Alors end inittete I 2RT-7807-2 paper tion Sr-90 Co-837 Co-137 contalruseygperse leeletion sad 1RT-7807-21 particulate e figure 9.4-2 filter Fleed y scintille-Cross y/ Be-131 10' *l0 2.3:10 l-131 5:10 Vital ec bwees Alors and initiate 1-131 conte tnseegyperse er, Chevroel tion /eingle I-13ty gf, feeletion f+ Certridge channel { em enelyrer 6x10'f/ plant vent i Offilne/ses p scintille= Crose p Kr-RS 10' -10 5.4 10/ Isl0 Instrumentaties Alere and inittste'

• g se bue cinevre of the JO IJfD Kr-85 Kr-85 weste gas discharge

[Q stech airhorne tion I (PVSA) ennitor valve g g.rs (2/3RT-7A08; w t/3 fleurgdj.49 2:10[',/ Instrumentation Alere end inttlete CA sh il Offline/ p scintille-Crose p Cl-36 & 10-10' IJfD/111D lootinctic/ tion Sr-90 2:10 se bus closure of the weste y Co-137 ses disc >erge velve w moving T paper par-O g,, titulate eg r filter l 3.3sj Instrumentation Alere and inittete t* offline/ y scintille-Groso y/ Real33 10 -10 6.5:10 2:10 [ / er bus closure of the weste gh tooninette/ tion / single 1-131 y IJfD t-13t 1-131 see discherac valve fined channel therroel snelyrer eart rider w ZOwO to t*

• < O th o
• -I w t'i n CE >

M i

c' .D m Table 11.5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION kt0NITORING (Sheet 3) pa N v Espected Alo re (IT Automette Actions S**pler/Mager, Actietty Celibretten penne Concentre}tene Setreing) Power Supply initiated Locatten j Quantity Sempler Type Detector Type Mee.ured leetere (pci/cmy) (pCE/r= ) (pce/cm 6.0e10 ' Instrumentatten Alera only padweste i Offline/ges F ociatille-Cross p Kr-R5 to -10 disposal ecce j tien tr-R5 oc bus (vent tRDAV) l 10-10' N 2:10 Instrumentation Alere only Istrbornemonitey Offline/ y scintille-Cress y Co-137 gg) ( 2 / 3RT -7809 ; toekinetic/ tien Be-133 Co-1}l ec bus { l figure 9,4-8 fined 2:10 I' Isl31 !ebeet 2) perticulete filter end chorroel cartridge 4 Offline/ges p scintille-Grose p Kr-85 to'0-lo'I N 6:10 Vital oc buses Alere end inttlete (FRAV)j Fuel handling Krag% leelettee of the feel handling stee free [ (2 per esopler tien aree went altberse sett) the norsel vestilo-ts eenster ties system and O (2RT-7822-1, actmetten of th, 3RT-7822 3, feel handling eres c$ W 2RT 7823 2, setident cleaner T m 7 3RT-7023-2; emit QM " O gp figure 9.4-9 N I offline/ y scintille-Crees y Co-137{g) 10-10' N 2:10 Vital oc buseo Alere and lattlete hp e sheet 2) Q. EM toeletten of the g W isekinetic/ tien Se-133 Co-l}{/ 2:10 fuel hend!!ss area J-131 free the eereel h q flued particalete veettlettee systen 2O ti) filter and end actuetten of O c'1 g of the feel bh cherceal cartridge handitag ares acci-g gn dent cleesup emit O At Centrol reen 2 offitee/ges p scintille-Crees p Er-85 to -10 IJtD 2 ID' Vital ec buseo Alere end tattiste

• I Kr-85 seeletten of the o

etrborne tien normel control rose t'S monitor ventilstesa systee hh (2/3RT-7824-1 and setuotten of t-j p 2/3RT-7825-2: the energency p figure 9.4-6 cienne, e,ete. sheet n Offline/ y scintille-Crees y Co-137/ 10-10' IJ1D 2:10 Vital er beece Alere and initiate y t* leeletten of the g teekinetic/ tien Se-133 Co-I}{/ fleed 2 30 nereal control y

x2 I-133 reos eentilation ow fD porticulate eyeten and actue-O filter and tion of the to g

[ cherceal emergency cleanup gg e cartridge Bik

A Q ,)- ,( s Table 11.5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION MONITORING (Sheet 4) Fmpetted Alere (1) Kampler/Magne Ai t t wi t y Cal 6hrstian Range Cancentragtans

• Setening)

Automatic Actions I.ar a t i an Qwantity Sempler Type Detectar Type Measured factape (pCi/rm)) (pci/re ) (pC6/re pawer Sep'te Initiated randraser air 2 offline/ses Law rente: Crnes P Er-85 10',-10'I 4.35:30' 9:30' inst rimentet ten Alere only ejetter ass (1 per P erlatella-Re-433 oc bee (CAI.C l un 69 ) tion g,y mon e t e r (7RT-74t2 and High range: Crees S Kr-85 10' -10 IJS 2:10'I Instrumentation Alere only 2 1RT-741R; P eclatille* Ie-133 oc bee fiacre 9.4-9 to n e eh 2) Condenser str 2 Oldline/sas Low range: Cross y Cl-17 10 to 4.3%e10' 9e10' Witel oc beses Alere only electar wide g,) (I per plastic 10 Xe-133 renne =anitor unit scintillater (Re-133) (2RT-7070 1 4 and lat-7470-1 flid ranger Cross g Cs-137 10 to IJS Titel oc buses 2 finere 9.4-9 solid state to sh 2) (Xe-133) - C w e.* liigh ranger Crose y Cs-137 10 to IJW Vital oc buses g, solid state 10 re e 4 CD (Re-133) Ch Offitne/ No detector T 4saklaetle/ toned par-terulate

• E.

t'l M "4 (n filter O2>gg otittne/ We detec tar esatinatic/ o fleed silver let meet t t e M e art r e dte m si &4 m t* w ZOwO to t*

• < O -

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w ,n h b p 1.,. c

• t.

Table 11.5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION MONITORING (Sheet 5) Espected gg Sempler/Mager Activity Celebration Range Concentregions Retpoint Automette Actlens 3 1.av a t i a. Quentity Sempler Type tietector Type Measured lootnpe (pC4/ceI) (pC4/em ) (pC6/cm ) Power Supply lattisted Cantainment 2 Offline/gse I.ow renae: Cross Y Cl-17 10". to S.410 '/ 1 10 Vitel oc buses Alere med tattlete purge and (I per pleetic to l>m Er-RS 6:10 cleomre of weste plant vent unit setatilletar (Xe-133) gas discharge valve steth wide

• to LMD Vital oc bwees rente Mid-sange:

Grass y Cs-137 10y (=witchable. solid state 10 2BT-7 PAS-1 and (tr.13 3) 1st-7A65-1 flaute 9.4-2 3 sh 2) Nigh range: Grose y Cs-137 lo to LMD Vital oc bases g solid state 10 (Xe-133) in Offline/ No detector 88 U toekinetic/ ftsed per-h titulate filter o E Offline/ No detector fy u teektnetic/ g., r3 PJ famed ellees . O- @ neellte rettridge 9W I 3 e M.s i n ar c am 4 Aree redle-Low range: Gross y Cs-117 10 to LPS 1.0ml0 Vital oc buses Alers 3o (A. Ifne montter (2 per tion monitor CM tube lo er/h ar/hr gQ g IP-331 wm (2RT-7875Al. unit) H Cl3 2RT-7874Al. I 3.0:10, Vital buses Alarm O 10'4 to LPs jut-7875Bl. 6 Arce redle-Nigh range. Cross y Cs-137 N 2aT-FR76RI. (2 per tien monitor tensretten 10 r/hr r/hr g Re-133 2 1st-7875Al. unit) chember O 1RT-7A74Al, M 3nT-7A75RI. 1RT-7974RI; O t-d figure 10.1-1) t!) 5 4-w T CwO in t~

• < O

- - ~ ~ tr) O Hw Mn h t

A. 0 o rs s Table 11.5-1 CON 11NUOUS PROCESS AND EFFLUENT RADIATION MONITORING (Sheet 6 of 6) F. spec t ed AlarmIII Aetometic Actions Artietty rat 6bretten pente Concentreginne Setpaing) Searler/Mager 3 (pCl/cm Power Sopply Initteted I.ar a r e na t)uant it y Sampler Tyre Detectar Type Measured Isatepe (ptt/re ) (pci/cm ) ~... - -. - 2 Normal eemple Area redise Law ranee Ernes, Caal17 10 to 100 mp/h - 5:10 mR/h Instrumentation Alere and feeletten lah lenletian t$en maatter of tube 10 mR/h at bue of normal operation semyle lab, mantear f2/197 781A. I Aree radia-N6th gente: Crass y C4 117 to to . I R/11 .5 R/h Instrumentottee and 2/19f-7819; t ien mon s t ee fantretten 10 p/hr at bue insure 9 14) theeher to I.MD 2 10 Uninterrupteble Alarm and initiate Steam senerattr 4 Offffne/ y Scfatti-f:rnee y C=-117 10'I ID' pawer eautre cleeiere of die-blawd. wen (5C50) liquid latinn charge valve ( 2 R T-47 %); 2RT-h759 t,) i )RI.h751 Os )RT-h759; g flaure 9.1-7 ) CO

• O e%

0. 89 GB 4 f' S 9J {' O 'tf W M 3 $,, -t H f/3 O Jtt M Eo tT! be th k4 -m ~ Z OwO th & WO th O N

x >

th V d am. A -1

i. San Onsfra 2&3 FSAR Updated RADIATION PROTECTION DESIGN FEATURES '{ Table 12.3-2 AREA RADIATION MONITOR LOCATIONS (Sheet 1) Alarm (b) Elevation Setpoints ,) Quantity Building (ft) (in.) Location (arem/h) 1 Auxilia ry 9 0 General area 2.5 (radwaste) 1 Auxiliary 24 0 Local sample lab 2.5 1 Auxiliary 37 0 High radioactive 10 storage area 1 Auxiliary 63 6 Waste gas surge 2.5 tank 2 Containment 63 6 Personnel access lock (1 per unit) Normal operation 15 Refueling 2.5 operation 2 Containment 30 0 General area (1 per unit) (TJ Normal operation 6.5 '/ Refueling 2.5 operation 2 Safety 8 0 General area 2.5 Equipment (Units 2 and 3) 2 Fuel 63 6 Spent fuel loading 2.5 Handling area (1 per unit) 1 Auxiliary 70 0 Radiochem lab 2.5 1 Auxilia ry 30 0 Control room 0.5 1 Auxiliary 37 0 General area 2.5 (radwaste) 1 Auxiliary 63 6 Hot machine shop 2.5 ~ 1 Auxilia ry 24 0 Post-accident 2.5 sample lab Total number of detectors for Units 2 and 3. a. b. Alarm setpoints are based on calculated gamma dose rates. Ala rm setpoints may be reset based on measured radiation levels. 1 / o 1 12.3-33

{' -Sen Onsfra 2&3 FSAR Updated RADIATION PROTECTION DESIGN FEATURES h Table 12.3-2 AREA RADIATION MONITOR LOCATIONS (Sheet 2 of 2) Elevation Alarm (b) Setpoints Quantity (,) _ Building (ft) (in.) Location (arem/h) 4 Containment 63 6 General area - safety-related (2 per unit) I Normal operation 625 Refueling-2.5 operation 2 Containment 93 0 High-range 10,000/ in-containment 100,000 monitors - safety-related (1 per unit) i Dual setpoints i s 2 Containment 98 0 High-range 10,000/ j-in-containment 100,000 4 monit rs - (I safety-related (1 per unit) Dual setpoints t-Vaj. 0 12.3-34 .i

r e ^ ',. TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) SPECIAL PROGRAM REVISION NUMBER: 1 h PAGE 36 0F 36 CATD LIST The following CATD identifies and provides corrective actions for the findings included in this report: 229.11(B) SQN 01 (12/18/86) 229.11(B) SQN 02 (12/18/86) { l l 1 1 L. a 1 1080d - 12/19/86 \\ l

g q f. J ECTG C.3 Attachment A Page 1 of 1 Revision 2 - A ECSP CORRECTIVE Action Tractina Document (CATD) j INITIATION 1. Imediate Corrective Action Required: 0 Yes % No 2. Stop Wort Recomended: 0 Yes J( No 3. CATD No. 12cf Il (6) %N of 4 INITIATION DATE / A- /$-F I-5. RESPONSIBLE ORGANIZATION: 6. PROBLEM DESCRIPTION: O QR O NQR TVR Dest uf D OCOsvt E M TATr oAl DE%C (LL P>E$ 9 OGT~- TM C Ca4 A-M G,E S M 4DE To -T'It E son em S. 5iN(_G_ TW E 5: 5 A (2. WA-5 L Asr 1.) P DATE D, TKE F%A (L SMooLD S E. tJPDAT E D To TEE PL E c.T rnes E

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m O ATTACHMENTS 7. PREPARED BY: NAME 0 3 O M IO)/ DATE: 'A-ef-Tc 8. CONCURRENCE]:gCEG-H hm VlWC PW DATE: / 2 -t o.K ? 9. APPROVAL: ECTG PROGRAM MGR9 DATE: CORRECTIVE ACTION 10. PROPOSED CORRECTIVE ACTION PLAN: 4 i-t) i l L O ATTACHMENTS 11. PROPOSED BY: DIRECTOR /MGR: DATE: 12. CONCURRENCE: CEG-H: DATE: j; SRP: DATE: ECTG PROGRAM MGR: DATE: VERIFICATION AND CLOSEOUT I i 13. Approved corrective actions have been verified as satisfactorily implemented. b. L l SIGNATURE TITLE DATE i.

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