ML20213A401
| ML20213A401 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/22/1987 |
| From: | Damon D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20213A334 | List: |
| References | |
| 229.11(B), 229.11(B)-R02, 229.11(B)-R2, NUDOCS 8702030259 | |
| Download: ML20213A401 (72) | |
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 REPORT TYPE:
SEQUOYAH ELEMENT TITLE:
RADIATION MONITORING SYSTEM (RMS)
Insufficient RMS Detection Equipment PAGE 1 0F 36 REASON FOR REVISION:
1.
Incorporation of TVA comments.
Revised to incorporate SRP and TAS conments and to add Section, Corrective 2.
Action.
PREPARATION PREPARED BY:
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DATE SIGNATURE CONCURRENCE 5
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- DATE APPROVED BY:$Af -
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l21s7 8Ix ECSPKANAGg DATE MANAGER OP buCLEAR POWER DATE CONCURRENCE (FINAL REPORT ONLY)
- SRP Secretary'.s signature denotes SRP concurrences are in files.
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROCRAM REVISION NUMBER:
2 l
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.
P 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 N0 X Identified by N/A Date N/A Documentation Identifiers:
None.
3.
DOCUMENT NOS., TAG NOS., LOCATIONS OR OTHER SPECIFIC DESCRIPTIVE IDENTIFICATIONS STATED IN El. MENT.
No document or tag numbers were stated in the concern.
The concern i
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 (ARPS).
The specific reference to "the shield building vent stack" radiation monitoring system causes it to be treated with special emphasis in this evaluation.
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1 TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER:
2 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
" File Screening Sheet" referred this concern to ECTG for b.
resolution or investigation (dated 06/24/86)
From the working file:
Form "D," "WBN Special Program on Employee Concerns 'K'-Form a.
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)
Form "G-A" states concern generic to several systems at WBN.
b.
SON had similar designs (dated 02/02/86) 5.
DOCUMENTS REVIEWED RELATED TO THE ELEMENT:
See Appendix A.
3 WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER 6.
APPLY OR CONTROL IN THIS AREA?
j l
See Appendix A.
LIST REQUESTS FOR INFORMATION, MEETINGS, TELEPHONE CALLS, AND OTHER 7.
DTsCUSSIONS RELATED TO ELEMENT.
See Appendix A.
1 1080d - 01/0P/87
r-TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 4 0F 36 P.
EVALUATION PROCESS:
Reviewed the SQN FSAR to establish detector quantity, type, a.
range sensitivity, and related requirements of each installation.
h.
Reviewed the requirements of Safety Evaluation Report and Supplements to establish initial SQN RMS compliance, Established present regulatory requirements for RMS.
c.
d.
Reviewed FSAR Sections of other PWR plants to establish presently accepted RMS practices in the nuclear power industry.
Reviewed TVA design documentation to determine the SQN RMS e.
level of compliance to current TVA guidelines and comitments.
f.
Compared the results of steps a, b, c, and d against e to p
evaluate the concern.
9.
DISCUSSION, FINDINGS, AND CONCLUSIONS:
Chronology:
This concern was raised initially on WBH 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.)
Ho 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 Therefore, the evaluator assumes that those parameters place.
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.
10P0d - 01/08/87
c TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 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 asstaned leakage conditions, as " radioactive process piping The term is further expanded by asstanption to include systems."
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 This " system" is actually a grouping of System (PERMSS). sampling / monitoring subsystems located at each selected processes that have a potential for carrying radioactive The CI is also quite specific about an insufficient i nventory.
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 tenn " radiation detection equipment," it is possible that the concern may also relate to the Area Radiation The PERMSS and the ARMS combined Monitoring System (ARMS).
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 l
public ( App. A, 6.a. b, c, d, e, f, g, h).
Using the above interpretations, the evaluator reviewed the entire I
Two different approaches were used; first, a general SQN RMS.
comparison with radiation monitoring practices at other PWRs, and, second, a verification review of the design criteria, design drawings, and FSAR against the SER findings.
j l
SQN PERMSS Description _
All PWRs have essentially the same basic sources of radioactivity in their process piping. Generally, any system that communicates l
with the Reactor Coolant System (RCS) or primary loop" is presumed l
to carry radioactive inventory. This is the case whether the i
communication is by direct piping connection or through heat exchanges and steam generators where leakage is presumed.
l l
1080d - 01/08/87
e TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 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 detect releases.
These monitors will vary from plant l
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 l
Auxiliary Building Vent Service Building Vent Containment Building Compartments (two levels) l Containment Building Purge Air j
Containment Building Personnel Hatch Post-Accident Sample Room l
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:
li Main Control Room Air Monitors Main Control Room Air Intake Monitors l
l As will be demonstrated later, mcnitoring of the above systems is directly consistent with the RitS practices at other licensed and operating PWRs.
1080d - 01/08/87 L
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION huMBER: 2 PAGE 7 0F 36 The SQN PERMSS is generally described in SQN FSAR Section 11.4 with particular attention to important parameters (sensitivity / range, 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 Design Criteria ( App. A, 5.Y) and the design drawings ( App. A, l
5.11,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.
SCH PERMSS Comparison 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 (The Standardized Nuclear Unit Power Plant System or 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 correlation, an objective professional judgment of SQN equivalence is easily drawn by the commonality.of the basic processes monitored. For 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 quantity of monitors required, but the release Ifmits are established by federal standards common to all plants.
Therefore, to ensure SQN compliance with these standards, the most key equipment parameter (i.e. sensitivity to trace isotopes setting the predominant nucleanic nature of the release effluent) were compared.
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER:
2 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 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 a predominant part of the gross mixture. These factors are comon to SON 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 Xe-Xe-133 Trace Isotope Kr-SS Kr-g5 10-}33 10-10-/
Sensitivity
- 10-9 10-9 10-Ic 10-12 Halogen Monitors 10-)8I-1 ; 10-1; I-13 Trace Isotope I -1 31 Ba-133 Sensitivity
- 10-0 10-0 10-'
10-/
- All sensitivities are given in terms of uCi/cc concentrations of the trace isotopes in question.
From this general comparison, the SQN PERMSS appears to be 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 a,nd sensitivity level.
Variations in individual plant designs are also reflected in the PERf1SS unique to cach plant. Even with these considerations, no obvious variance that would identify deficiencies in the SQN PERMSS is evident.
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 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.
It can be seen, therefore, that a monitor having a sensitivity of, say 10-7 uCi/cc in a 0.1 mR/hr background would only have a 10-$ uCi/cc sensitivity if the background were 1.0 mR/hr.
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., PVhGS, SQN) want to have more latitude in the final location of the monitor and so they will a plant induced background of 1.0 mR/hr. and accept a lower assume sensitivity statement even though the monitors may be identical.
Another variable in background noise may be the amount of margin the designer wants in avoiding spurious alarms due to environmental 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.
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER:
2 PAGE 10 0F 36 The manner in which the signal-to-noise ratio is specified.also af fects sensitivity. The "not signal equal to background" statement noted earlier is very conservative.
Less conservative approaches are where the standard statistical deviation of the hackground 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)."
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 CPf1 and the "95% SCL" about 20 CPM.
The isotopic concentration 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 though the equipment was identical.
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 uti/cc if it sampled a long lived isotope for 12 minutes, but could be said to have a sensitivity of 10-Il uCi/cc if it sampled for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
For these and several deeper technical reasons (e.g., secular equilibrium where decay times approach sampling times) the very same monitors can have sensitivity statements that differ by a decade or more.
The detection equipment used in radiation monitoring systems, which is what really establishes base sensitivity, is all essentially the 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 nethods used to describe the systems.
With these considerations in mind, the evaluation team finds that the SQN monitors seem directly consistent with PVNGS and acceptably close to SONGS, and SNUPPS to be considered equivalent.
In all cases, the monitors sen'sitivities are well in excess of those required by the federal guidelines in the following section.
1 10F0d - 01/08/87
TVA EMPLOYEE CONCERNS REPORT hlMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NtMBER:
2 PAGE 110F 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.
The operational limits placed on release of radioactive materials are established by 10 CFR 20 ( App. A, 6.f).
This is to be contrasted with Section 50.34a of 10 CFR 50 ( 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 10 CFR 50 sets out three general design criteria in this regard l
L (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 nonnal reactor operation, including anticipated operational occurrences. Sufficient holdup capacity shall be provided for retention of gaseous and liquid effluents containing radioactive materials, particularly where unfavorcble site 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.
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10P0d - 01/08/87 l
TVA EMPLOYEE CONCERNS REPORT NLMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 12 0F 36
" Criterion 64 - Monitoring radioactivity releasen. 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 10 CFR 50 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 (beta), or gaseous effluent estimated annual external dose of 5 millirems (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 This applies to particulate isotopes as well.
The organ.
concluding statement of the Annex to Appendix I establishes a 5 millirem total body or any 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 (todines 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.
Of the relevant Regulatory Guides, Reg. Guide 1.21 ( App A, C.9) most directly addresses implementation of the 10 CFR 20 operating l
I 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 10-9 uCf /cc for being equivalent to 10P0d - 01/08/87
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
REVISION NUMBER:
2 PAGE 13 0F 36 the 10 millirad (gamma) and 20 millirad (beta) limits of Appendix !.
Iodine and particulate measurements are set at the 15 millirem organ (thyroid) levels.
Tritium is treated as a special case of gas with a minimum detectable concentration of 10-6 uC1/cc.
Gross activities of 10-7 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 1
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)
SON 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 10 CFR 20, 10 CFR 50, 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.B. II.C. and 11.0 of Appendix I to 10 CFR Part 50."
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SPECIAL PROGRAM REVISION NUMBER:
2 PAGE 14 0F 36
" Based on our evaluation, as described below, we find the propose.1 liquid, gaseous and solid radioactive waste systems and associated process and effluent radiological monitoring and sampling systems to be acceptable."
Referring more specifically to menitoring and sampling equipment locations and types, the NRC stated in Section 11.2 of the SQh SER:
"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 release pathways are monitored. We have also determined that the sampling and monitoring provisions are adequate for detecting radioactive material leakage to nomally 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, and Reporting Rad,foactivity Solid Wastes and Releases of Radioactive Haterials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plant'".
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 monitoring all normal and pctential effluent discharge paths in conformance with General Design Criterion 64, for providing automatic termination of 'offluent releases and assuring control over releases of radioactive materials in effluents in conformance with General Design Criterion 60 and Regulatory Cuide 1.21, for sampling and monitoring plant 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 Regulatory Guide 1.21, and for monitoring process and effluent streams during postulated accidents.
The review 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 systems are acceptable 10P0d - 01/0P/87
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION h0MBER: 2 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, 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 statements, was supported by the actual design, the evaluation team also compared both SER findings and the SQN FSAR with the current SQN PERMSS Design Drawings (App. A, 5.mm through 5.ss), the RMS procurement specifications ( App. A, 5.cc thru 5.ff), and the SQN llechanical Instrument Tabulation ( App. A, 5.00), which establishes setpoints.
This review confimed that the "as designed" SQN RMS supported the hRC SER findings of compliance with federal guidelines.
In the course of these evaluations, it was noted that design improvements have been made to the PERMSS since the NRC filed its SER.
Therefore, the initial NRC finding of adequacy has been enhanced since that time.
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 design documentation were noted. For example, Design Criteria SCN-DC-V-9.0 ( App. A, 5.v) paragraph 3.5.2.1 stipulates that the Condenser Vacuum Pump Exhaust Vent Monitor is "to satisfy the requirements of Regulatory Cuide 1.45."
This is a physical impossibility because Regulatory Guide 1.45 requires detection of the reactor coolant pressure boundary Icaks to containment and a communications path from containment to the condenser does not exist.
The discrepancies noted, however, did not result in RMS deficiencies that would conflict with federal guidelines or invalidate the hRC's original findings of adequacy.
In fact, the design documentation shows enhancements that would substantiate such findings more today than when originally made.
It should be noted that the NRC SER did not review changes required following the incident at ihree Mile Island.
This is a dif ferent issue and is addressed later in this report.
The investigation conducted to this point merely confims 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 validating the SER and by independent comparison with other licensed and operating PWRs.
10P0d - 01/08/07
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 16 0F 36 Shield Building Vent Stack The concern contains a specific reference to the " shield building l
vent stack" which includes nomal 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 SON 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 (uCf /cc)
Unit SON 1
10-6 Kr-65 10-9 Cs-137 10-9 I -1 31 PVNGS 1
10-6 Kr-65 10-9 Cs-137 10-9 Ba-133 SONGS 1
10-7 Xc-133 10-12 (s.137 10-11 1 131 SNUPPS 1
10-7 Xc-133 10-12 Cs-137 10-11 1-131 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 Whatever the changes on several plants using a standardized design.
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 kRC SER.
10F04 - 01/0P/87
1 TVA KMPLOYRE CONCERNS REPORT NUMBER: 829.11 (8)
{
SPECIAL PROGRAM REVISION NUMBER:
2 1
I PAGE 17 0F 36 I
Post Three Mile island Channes
)
l 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) i and initiated an action plan (App. A. 6.0) to institute changes. Two of j
these changes affected the SQN RMS; NUREG 0737 (App. A. 6.p) and j
Regulatory Guide 1.97 (App. A 6.k).
Each set of requirements was l
l 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.
l i
NUREG-0737, Supplement 1 provided guidance that called for additional j
radiation monitoring capability (App. A. S.f).
In response, TVA added 4
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 Dlowdown and Condenser Air Ejection i
monitors were considered sufficient for this purpose.
i Review of the design drawings ( App. A. 5.mm thru S.ss) and the SQN Design i
Criteria for RMS, SQN-DC-V-9.0 (App. A, S.v) confirmed follow-through on i
1 equipment changes and additions necessary to meet NUREG-0737. The following radiation monitors are addressed by this latest version of the SQN Design Criteria:
\\
i Condenser Vacuum pump Exhaust Vent Monitors i
Shield Building Vent Monitors Auxiliary Building Vent Monitor
(
Main Control Room Airborne and Area Monitors Main Control Room Air Intake Monitors i
Containment Building purge Air Exhaust Monitors
}
Containment Building Personnel llatch Monitor j
Post-Accident Sample Room Monitor i
ruel Pool Monitors l
Steam Generator Blowdown Line Monitors Residual Heat Removal Line Monitors l
Reactor Coolant Drain Discharge Monitors Station Sump Discharge Monitor i
l plant I.iquid Discharge Monitor Containment Building Floor and Equipment Drain Sump Discharge l
Monitors i
containment Building Upper and Lower Compartment Monitors i
i i
l I
i 1080d - 01/08/87
"""MW-**'yTg yt ygrM-Tyw-t
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 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 Appendices C and D.
These tables show the additional RMS equipment to meet NUREG-0737, Supplement I requirenents.
IJRC Regulatory Guide 1.97 (Rev. 2)
Both NUREG 0737, Supplement 1 and Regulatory Guide 1.97 (Rev. 2) resulted fran lessons learned at Three Mile Island. Where NUREG 0737, Supplement I required the addition of RMS capability, Regulatory Guide 1.97 dealt with how monitoring infonnation was to These post be enployed in following)the course of an accident.requirenents mostly ma accident monitoring (PAM instrumentation already in the plants but, in many cases, added requironents (e.g., seismic and environmental qualification) necessitated new procurement at many facilities, including SQN.
With the addition of the NUREG 0737, Supplement i equipment outlined above, SQN had sufficient RMS equipment to meet these minimum requirenents of Regulatory Guide 1.97.
In March 1982, TVA submitted a timely response to the PAM Requirenants of the Regulatory Guide 1.97 (App. A, 5.q).
Correspondence and documentation following the fiarch 15, 1982 submittal ( App. A, 5.u, jj, tt, uu, vv) indicates that TVA has prograns in place that are making assessments and modifications to what will be implemented at SQN to meet Reg. Guide 1.97, Rev. 2.
Final resolution and implenentation of this issue are being deferred fron Septonber 1987 to the SQN Unit 2, Cycle 4 outage (App. A, S.vv) and are not an issue in this concern.
art 1S Comparison With Other PWRs While the concern cicarly refers to the PERiiSS, it did not specifically exclude the ARMS. Because the ARMS detects only mean ga:nna radiation levels to preestablished guidelines limits, the type of equipment used is fairly unifonn fran plant to plant.
The quantity and location of such detection equipment, however, is unique to plant type (BWR or PWR) and individual plant procedures and arrangenents.- Therefore, conparison of the SQN ARMS to other units would not provide fully verifiabic conclusions.
However, a general correlation as to equipment paramotors is possible.
The SQN ARtiS is described in SQN FSAR Section 12.1.4.
The equipment described has the same features connonly found in other state of the art systems (e.g., G-M detectors, built-in check sources, five-decade range, alanas, annunciation, recording, etc.).
1080d - 01/08/87
d TVA EMPLOYEg CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 19 0F 36 The adequacy 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 concentrstions that are a significant fraction of those given in 10 CFil Part 20, Appendix B. Table I.
Additionally, two monitors provide b
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 e
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 l
satisfactory radiological protection to inplant personnel;"
~
The number of monitors used at SQN (20) was a bit less than at other units (see attachments). 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-ISF" area monitors and 4 "ESF" monitors. This is roughly equivalent to SQN, however, Palo Verde also makes extensive
't 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 evidence that would conflict with the above NRC SER finding. The ARMS has "enough radiation detection" to " meet federal guidelines."
Eindings:
a.
The SQN RMS has sufficient detection and sampling capability to meet the requirements of 10 CFR 20, 10 CFR 50 (including both Appendix A and Appendix I), Regulatory Guides 1.21, 8.8, 8.10, l
NUREG 0737 and NUREO 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.
s a
1080d - 01/08/87
3 4
O TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) ti SPECIAL PROGRAM REVISION NUMBER: 2 a,
t*
PAGE 20 OF 36 b.
The present process piping RMS, including ventilation systems, monitor all systems having a reasonable potential for 4 "v 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.
The 'hield Building Vent Stack RMS has sufficient equipment to
'J S
c.
meet 10 CFR 20, 10 CFR 50 and Regulatory Guide 1.21 l
requirements. It has been modified and expanded to meet NUREG 0737 and NUREG 0737 Supplement 1 post-TMI requirements.
==
Conclusion:==
7 7~
The concern is not valid. The present SQN RMS meets the normal
~.g.
.operatinE requirements of 10 CFR 20, 10 CFR 50, including both l
1 Appendix A'and Appendix I, and Reg. Guide 1.21.
The validity of the initial NRC SER supporting the SQN operating license is confirmed.
l The present SQN RMS, as modified and expanded since TMI, meets the
, ;i^ 3 requirements of NUREG 0737 and NUREG 0737, Supplement 1.
Some J
confusion.about the RMS configuration may have occurred because of the discrepancy between the design criteria and design drawings and the FSAR. 'The FSAR should be updated to reflect the post TMI improve'ents to the SQN RMS.
m 10.
CORRECTIVE ACTION The corrective action plan (App. A 5 ww) indicates that the post TMI, additional monitoring requirements, presently in the design
'r drawings and the SQN RMS Design Criteria, will be added to the SQN i
FSAR in the next annual revision.
i The revision to the TVA Design Criteria SQN-DC-V-9.0 Rev.2 is for clarification only, and is not warranted at this time.
t I
's t
l
(
sw i
I i
i i
10kOd-01/08/87 y
?
.x
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE il 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" I
SQN Safety Evaluation Report, (03/79), Supplement 1, (02/80),
b.
Supplement 2, (08/80) 10CFR50, "Danestic Licensing of Production and Utilization c.
Facilities," Appendix A, Appendix I 10CFR20, " Standards for Protection Against Radiation" d.
NRC Regulatory"GuideHeasuring, Evaluating, and Reporting e.
1.21, Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents fran 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, "Infonnation Relevant to Ensuring that Occupational Radiation Exposures Will Be as Low as Reasonably Achievable" 8.10,
" Operating Philosophy for Maintaining Radiation Exposures as Low as Reasonably Achievable (Nuclear Power Reactors)"
NUREG-0737,. Supplement 1, " Clarification of TMI Action Plan f.
Requirements," (11/80),Section II.F.1, " Additional Accident Monitoring Instrianentation" San Onofre Nuclear Generating Station Units 2 and 3, FSAR g.
Section 11.5, Table 11.5-3 Palo Verde Nuclear Generating Station, Units 1, 2 and 3, FSAR h.
Section 11.5, Table 11.5-1 1080d - 01/08/87
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 22 0F 36 APPENDIX A (cont'd) 1.
Standardized Nuclear Unit Power Plant Systems (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. H. Mills, TVA, to L. S. Rubenstein, NRC, NEB 800404 588, (04/02/80)
Letter from L. M. Mills, TVA, to A. Schwencer, NRC, m.
A27 810212 017, (02/12/81)
Letter from H. R. Wisenburg, TVA, to E. Adensam, NRC, n.
A27 810701021, (07/01/81) o.
Letter from L. M. Mills, TVA, to E. Adensam, NRC, A27 810904 019, (09/04/81)
Letter from L. M. Mills, TVA, to E. Adensam, NRC, p.
NEB 811113 627, (11/06/81)
Letter from L. M. Mills, TVA, to E. Adensam, NRC, q.
A27 820315 096, (03/15/82)
SQN Employee Concern 230.5, "HVAC Design - Radioactivity in r.
the CDWE Building" TVA Conference Notes (B43 860723 902), " Post Accident s.
Monitoring System," (07/02/86) t.
TVA memo from B. Hinnanpour to SQN Files, (B25 860909 015),
"SQN Accident Monitoring Meeting of August 27, 1986,"
(09/09/86)
Letter, J. O. Vantrease, Impe11, to G. W. Painter, TVA, u.
" Revision 1 to Proposal for Regulatory Guide 1.97, Rev. 2, Compliance Program," (10/13/86)
TVA Detailed Design Criteria No. SQN-DC-V-9.0, "Sequoyah v.
Nuclear Plant Radiation Monitoring System," R2 (07/14/86) 1080d - 01/08/87
TVA EMPLOYEE CONCERNS REPORT NIMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NIMBER: 2 PAGE 23 0F 36 APPENDIX A (cont'd)
TVA Design Criteria No. SQN-DC-Y-9.0, "Sequoyah Nuclear Plant w.
Radiation Monitoring System," R1 (03/10/86)
TVA Hechanical Design Guide DG4118.7.1, " Radiation Protection x.
( ALARA) Design Guidelines," (11/20/81)
TVA Mechanical Design Guide DG-M18.7.11, " Radiation y.
Protection Features for Nuclear Plant Accidents," (05/31/83)
U. S. Nuclear Regulatory Commission, "TMI-2 Lessons Learned z.
Task Force Status Report and Short-Term Recommendations."
USNRC Report NOREG-0578, July 1979, Recommendation 2.1.8.b.
American National Standards Institute, " Guide to Sampling aa.
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, (NRC), to All Operating Plants, (10/30/79)
TVA Contract J2-826848, " Isokinetic Stack, Sampling Station,"
cc.
Air Monitor Corporation (12/10/79) dd.
TVA Change of Contract 72C61-92759, " Radiation Monitors,"
General Atomic Company (12/12/80) ee.
TVA Purchase Requisition Nunber 829854, " Emergency Purchase -
Effluent Radiation lionitors," (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 /1 4/81 )
Letter from D. G. Eisenhut, NRC, to All Operating Nuclear f
gg.
Power Plants, (09/13/79) hh.
Letter from H. R. Denton, NRC, to All Operating Nuclear Power P1 ants (10/30/79) 11.
Regulatory Guide 1.97, " Instrumentation to Follow the Course of an Accident," Rev. 3 (08/83) 1080d - 01/08/87 f
e TVA EMPLOYEE C0llCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 24 0F 36 APPENDIX A (cont'd) jj.
TVA DE Calculation SQN-SQS4-0052, "PAM Variable Detennination in Accordance with Reg. Guide 1.97, R2 (Types A, B, & C (07/30/86) f kk.
TVA OE Calculation SQU-SQS4-0068, " Type D & E Variables in Accordance with Reg. Guide 1.97, R2" (09/11/86) m.
-1 R10
" Wiring Diagrams Radiation Monitoring System, Schematic Diagrams Sheet 1"
-2 R12
" Wiring Diagrams Radiation Monitoring System, l
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 lionitoring and Sampling" 0o.
SQN TVA Drawing 47B601-90-0 "Hechanical Instrument Tabulation" pp.
SQN TVA ' Drawing Series 47W600:
-100 R13, "liechanical Instruments and Controls"
-101 R6,
" Mechanical Instruents and Controls"
-102 RI O,
" Mechanical Instruents and Controls"
-103 R4, "itechanical Instruments and Controls" l
-104 Rl 9,
" Mechanical Instruments and Controls" l
-105 R10 "ilechanical Instruments and Controls" l
-106 R14,
" Mechanical Instruments and Controls"
-107 R9, "Hechanical Instruments and Controls"
-108 R0, "liechanical Instruments and Controls"
-109 R4, "Multiline Shield Building Seals" l
-110 R3,
" Mechanical Instruments and Controls, Pneu I
& Elec Test Bench" l
-111 R3,
" Mechanical Instruments and Controls, Pneu
& Elec Test Bench Det"
-112 R1,
" Mechanical Instraents and Controls, Pneu
& Elec Test Bench Det" l
-301 R4,
" Mechanical Instruents and Controls"
-302 R2, "liechanical Instruments and Controls" 1080d - 01/08/87 i
TVA EMPLOYEE CONCERNS REPORT HlMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NIMBER: 2 PAGE 25 0F 36 APPENDIX A (cont'd) qq.
SQN TVA Drawing Series 47W610: 1 R19,
" Mechanical-Control Diagram - Radiation Honitoring 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 Diagram - Radiation
' Monitoring System" rr.
SQN TVA Drawing Series 47W611: 6 R16
" Mechanical Logic Diagram 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 Sanpling 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 RS,
" Mechanical-Radiation Sampling System -
Auxiliary and Reactor Building"
-7 R13,
" Mechanical-Radiation Sampling System -
l 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 Rio, " Mechanical-Radiation Sampling System -
Auxiliary and Reactor Building" i
1 1080d - 01/08/87
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM.
REVISION NUMBER: 2 PAGE 26 0F 36 APPENDIX A (cont'd)
-12 R7, " Mechanical-Radiation Sampling System -
Auxiliary and Reactor Building"
-13 R6,
" Electrical-Radiation Sampling System -
Auxiliary and Reactor Building"
-14 R9, " Mechanical-Radiation Sampling System - Post Accident"
-15 R10. " Mechanical-Radiation Sampling System - Post Accident"
-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 -
Auxiliary and Reactor Building" i
-20 R3,
" Mechanical-Radiation Sampling System -
Auxiliary and Reactor Building"
-21 R0,
" Mechanical-Radiation Sampling System - Post Accident"
-52 R1,
" Mechanical-Radiation Sampling System -
Auxiliary and Reactor Building"
-53 R1,
" Mechanical-Radiation Sampling System -
Auxiliary and Reactor Building"
-54 R1, " Mechanical-Radiation Sampling System -
Auxiliary and Reactor Building" 3
-56 R1, " Mechanical-Radiation Sampling System -
Auxiliary and Reactor Building" tt.
Letter from L. Lt. Mills, TVA, to E. Adensam, NRC, No. A27 830304 001 (03/14/83) uu.
Letter from E. Adensam, NRC, to H. G. Parris, TVA, 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) w.
TCAB-051 Corrective Action Plan Transmittal for CATD 229.11 SQN 01 and CATD 229.11 SQN 02 (01/07/87) 1 1080d - 01/08/87
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 27 0F 36 APPENDIX A (cont'd) 6.
WHAT REGULATIONS, LICENSING COMMITMENTS, DESIGN REQUIREMENTS OR OTHER APPLY OR CONTROL IN THIS AREA?
10CFR50, Damestic Licensing of Production and Utilization a.
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" 10CFR50 Appendix A, General Design Criterion 63, "Honitoring c.
Fuel and Waste Storage" d.
10CFR50, Appendix A, General Design Criteria 64, " Monitoring Radioactivity Releases" 10CFR50, Appendix I, " Numerical Guides for Design Objectives e.
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, "Infonnation Relevant to Ensuring that Occupational Radiation Exposures Will Be as Low as Reasonably Achievable," R3, (06/78) 1.
NRC Regulatory Guide 8.10, " Operating Philosophy for Maintaining (Radiation Exposures as Low as Reasonably Achievable Nuclear Power Reactors)," R1, (05/77) j.
NUREG-0737, Supplement 1, " Clarification of Till 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) 1080d - 01/08/87 6.
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 28 0F 36 APPENDIX A (cont'd) 1.
FSAR Section 11.4, " Process and Effluent Radiological Monitoring and Sampling System" m.
FSAR Section 12.1.4, " Area Monitoring" n.
NUREG-0578, "THI-2 Lessons Learned Task Force Status Report and Short Term Recommendation," (July 1979) o.
NUREG-0660, "NRC Action Plan Developed as a Result of the THI-2 Accident," (May 1980)
NUREG-0737, " Clarification of TMI Action Plan Requirements,"
p.
(November 1980) 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. (. Damon, Bechtel,.R. Cornwall, TVA, October 21, 1986 Phone Conference, D. L. Damon, Bechtel, P. B. Nesbitt, TVA, Decenber 4,1986.
1080d - 01/08/87
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 29 0F 36 ATT'ACHMENT NO.1 SQN FSAR a.
Table 11.4.2-1 Liquid Radiation Monitors I
i 1080d - 01/08/87
m
~.
SNP TABLC 11.6.2-1 Lif)Ul0 RADIATION 940NITnas toe.tlen batter stonitor Tile and Assembly Seleele Floor Oechground ta pec t ed Conc Ouentity 8
(ma/h)
Det ectar Type Range Seele er Red Smeele etwe eur e d 3
Type TVA Instr lie.
gen,tlig Close
_t[l_
Weste Dloposal 0-85-90-122 t/plent Il 669.0 Aus 1.0 Comes in*0 to 10*I eCl/cc 10 to in4 c pe 1.% a 10*O crees 5 fetes I.lguld Scintilletian Conc Effluent mnitor taeontlel new 0-02-90-131, 2/plent t
690.0 Aus 3.0 8:eeme 10*0 to IO*I WCl/ec 10 to 106 steellalble Crees cpe Scintillation Conc Coollag Water 114. 440. 141 Liquid sbnitor Cnerenent Cnallag 0-RE-90-121 3/plent t
714.n Ave 1.0 Ceeme 10-6 g, 30-1 pCl/cc to to 106 toeglislble Creee c pe Systee Liguld l-at-90-I21 Sc i nt i l la t ion Cese tffluent Monitor 2-RE-90.-121 Stese Generator 1-at-90-120 2/ plant Il 734.0 Aus 1.0 Comme 10*0 to 10*I pCl/ec 10te In6 e pe S e to-6*
Crees aloudoun Discherge 128 Scintillation (mac Seeple 2-RE-90-120 2/ plant
% nitor teorereter ran-I-82-90-870 2/ plant il 690.0 Aes 10.0 Comes 10-6 g, go-l uC1/cc t o t e In' r pe Ie to-6 Crees done.* e Sc in t i l l a t ion Conc Liguld Ef fluent 7-85-90-170 Monitor neector Coolent 1-85-90-806 2/plent I
754.0 Ave 1.0 Gemme 10~0 to IOI hcl /cc 10 to In" c pe Table ll.l.l*?
Crees Sc in t i l l a t ion Come latJown Liquid 2-8E-90-104 Moniter St ees Generator I-85-90-824 21 plan
- II 714.0 Aus 1.0 r.emme In*6,, go-l PCI/cc I n t o Isi em
% e 10-6 Crees
~
h ScInttilation Canc
(
Sletadoun Liquid l
Montter l
l
- 1f reverse nemools concent rat es are being discharged, the concent rat ion ut il be shout ten flees value sadicated.
l
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B) f SPECIAL PROGRAM
?
REVISION NUMBER: 2 PAGE 30 0F 36 ATTACINENT NO. 2 SQN FSAR a.
Table 11.4.2-2 Gaseous Radiation Monitors s
l l
1080d - 01/08/87 e
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-3 c m e:ov e -
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s.s e
e J c ;.e g b< u.c.-
es. 8.
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6 4
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V D a
er g
g C
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3 I
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a a
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 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 1
t 1080d - 01/08/87
RADIATION P0NITORING SYSTEM SQN-DC-V-9.0 TABLE 9.0-1 PONITUR DESCRIPTION i
Monitor Function Ins trtsnent Channel Monitoring Control Notes Monitor Ntsnber Qty Detector Type 1.
Gaseous Effluent Monitors Condenser Vacusse Ptanp Exhaust vent Normal Range 1-RE-90-Il9 2/ Plant Offline Beta Scint.
Yes No 7
High Range 1-RE-90-99 2/ Plant Offline Beta Seint.
Yes No 7
Accident Range (Interim) 1-RE-90-255&256 2/ Plant Online G-M Tube &' Ion Clusbr.
Yes No 7
Accident Range 1-RE-90-404 2/ Plant Offline G-M Tubeg Yes No 7
Shield Building Vent Normal Range Particulate 1-RE-90-100A 2/Plet Offline Filter & Beta Scint.
Yes No 5,7 Noble Gas 1-RE-90-1005 2/ Plant Offline Beta Scint.
Yes No 5,7 todine 1-RE-90-100C 2/ Plant Offline Filter &G-M Tube Yes No 5,7 Particulate, Noble Gas, lodine 1-RE-90-400 2/ Plant Of fline Ccusposite Det.
Yes No 7
Accident Bange (Interim) l-RE-90-260&261 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 Of fline Beta Scint.
Yes Yes 5,7 lodine O-RE 101C 1/ Plant Of fline Filter & G-M Tube Yes Yes 5,7 Contairusent 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 k.-.ATION PtNITtRING SYSTEM SQN-DC-tf-9.0 TABLE 9.0-1 (Cont inued) tt)NITOR DESCRITIlON Monitor Inst rtsnent Channel Detector Function Monitor Ntsnber Qty Type Monitoring Control Notes II.
Liquid Ef fluent Monitors Plant Liquid Discharge 0-RE-90-211 1/ Plant Offline Gamma Scint.
Yes No 8
Station Sep Discharge 0-RE-90-212 1/ Plant Offline Gamma Scint.
Yes No 8
Reactor Coolant Drain 1-RE-90-277 2/ Plant Online G-M *1bbe Yes Yes Tank Discharge.
1-RE-90-278 2/ Plant Online G-M Tube Yes Yes Contairusent Bldg Floor and Eqpt.
1-RE-90-275 2/ Plant Online G-M Tube Yes Yes Drain Sump Discharge 1-RE-90-276 2/ Plant Online G-M Tube Yes Yes 111. Process Monitore 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 Path 0-RE-90-205 1/ Plant Offline Beta Scint.
Yes No 8
0-RE-90-206 1/ Plant Of fline Beta Scint.
Yes No 8
Fuel Fool Air Space 0-RE-90-102 1/ Plant Area G-M Tube Yes Yes 8
0-RE-90-103 1/ Plant Area G-M Tube Yes Yes 8
Steam Generator Blowdown Lines Ccammon Header 1-RE-90-120&l21 2/ Plant Offli ne t'-== Scint.
Yes Yes 7
Individual Sample Lines 1-RE-90-124 2/ Plant Offline Cause Scint.
Yen No 7
Residual Heat Removal Lines 1-RE-90-290,291 2/ Plant Online G-M Tube & Ion Clumbr.
Yes No 7
l-RE-90-292,293 2/ Plant Online G-M Tube & Ion Chmbr.
Yes No 7
E86188.01 R m
RADIATION !ONITWING SYSTEM SQN-DC-V-9.0 TABLE 9.0-1 (Continued)
MONITOR DESCRIPTION Monitor Instrtsnent Channel Detector Punction Monitor Nunnber Qty Type Monitoring Control Notes IV.
Airborne Monitors Main Control Room 0-RE-90-105 1/ Plant Part Filter & Beta Scint.
Yes No 8
Contairunent Bldg. Upper Compartment Normal Range Farticulate 1-RE-90-ll2A 2/ Plant Offline Filter & Beta Scint.
Yes Yes 5,7 Noble Gas 1-RE-90-112B 2/ Plant Offline Beta Scint.
-Tes Yes 5,7 lodine 1-RE-90-112C 2/ Plant Offline Filter &G-M Tube Yes No 5,7 Accident Range 1-RE-90-271 2/ Plant Area Ion Chanber Yes No 7
l-RE-90-272 2/ Plant Area Ion Chanber Yes No 7
Contairunent Bldg. Lower Ccampartment Normal Range Particulate 1-RE-90-106A 2/ Plant Offline Filter & Beta Scint.
Yes Yes 5,7 Noble Ces 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 Chanber Yes No 7
l-RE-90-274 2/ Plant Area Ion Chanber Yes No 7
Outside Contairunent Building Personnel Hatch 1-RE-90-2 2/ Plant Area G-M Tube Yes No 7
V.
Area Monitors Main Control Room 0-RE-90-135 1/ Plant Area G-M Tube Yes No 8
Post Accident Sanple Room 1-RE-90-280 2/ Plant Area G-M Tube Yes No 7
E86188.01 TVA EMPLOYEE CONCERNS REPORT MUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 32 0F 36 ATTACHMENT NO. 4 SQN DESIGN CRITERIA SON-DC-V-9.0
" Radiation Monitoring System" a.
Table 9.0-2 Monitor Safety Requirements t
l 1080d - 01/08/87
11AT10N M(NITORINC SYS1TM SQN-E-V-9. 0 i
TABIZ 9.0-2 MONITOR SAFETY REQUIREMENTS Instrument Safety Clans Seismic Elect Vital knitor Ntrnber Mech Elec Category Separation Power Redundant Notes 1.
Caseous Ef fluent Nnitors Condenser Vacuum Pts, Exhaust Vent Normal Range 1-RE-90-119 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 Hone Note 2 No 9
Shield Building Vent Normal Range Particulate 1-RE-90-100A B
None Note 1I None No No 5,9 Noble Ces 1-RE-90-100B B
None Note 11 None No No 5,9 Iodine 1 -RE-90-100C B
None Note 11 None N
No 5,9 Particulate, Noble Cas, Iodine 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
Auxiliary Building Vent Particulate 0-RE-90-101 A S
IE I
TRN A/1RN B Yes No 4,5,9 Noble Gas 0-RE-90-101B S
lE I
1RN A/TRN B Yes No 4,5,9 Iodina 0-RE-90-101 C S
lE I
TRN A/TRN B Yes No 4,5,9 Contairusent Bldg Purge Air Yxhaust 0-RE-90-130/131 S 1E I
TRN A/TRN B Yes Yes 9
E86188.01 m,
RADIATION 10NITORING SYSTEM SQN-DC-V-9.0 TABLE 9.0-2 (Continued)
MONITOR SAFEIT REQUIREPENTS Ins t rtsnent Safety Class Seismic Elect Vital Monitor Ntsnber Mech Elec Category Separation Power Redundant Notes II.
@id Effluent Monitors Plant Liquid Discharge D-RE-90-211 H
None None None No No 9
Station Stamp Discharge 0-RE-90-212 H
None None None No No 9
Reactor Coolant Drain Tank Disch.
1-RE-90-277/278 NA lE I
1RN B/TRN A Yes Yes 1
Contairusent Blds Floor and Eqpt Drain Stssp Discharge 1-RE-90-275/276 NA lE I
TRN B/TRN A Yes Yes 1
III. Process Monitors Main Control Room Air Intake Normal Path 0-RE-90-125/126 C IE I
TRN A/TRM B Yes Yes 9
Emergency Path 0-RE-90-205/2% C IE I
TRN A/TRN B Yes No 9
Fuel Pool Air Space 0-RE-90-102/103 NA lE I
TRN A/TRN B Yes Yes 1
Steam Generator Blowdown Lines Caumon Header 1-RE-90-120&l21 H None None None No No 9
Individual Sample Lines 1-RE-90-124 C,B None Note 11 Nooe No No 6
Residual Heat Removal Lines 1-RE-90-290&
NA 1E I
TRN A/TRN B Yes No 1
l 291/292&293 E86188.01 o
ADI ATION KNITCCING SYS17M SON-DC-V-9.0 TABII 9.0-2 (Cont inued)
MONITOR SAFETY REQUIREMENTS Ins trument Safety Class Seimnic Elect Vital
&nitor Ntsnber
&ch Elec Category Separation Power Redundant Notes IV.
Airborne k niters Nin Control Room 0-RE-90-105 NA Hone I
None No No 1
Contairment Bldg Upper Coupartment Norinal Darge Particulate 1-RE-90-Il2A B
IE I
TRN B Yes Yes 5,9,10 Noble Gas 1-RE-90-112B B
IE I
1RN B Yes Yes 5,9,10 Iodine 1-RE-90-ll2 C B
IE I
1RN B Yes No 5,9 Accident Range 1-RE-90-271/272 NA lE I
TRN A/TRN B Yes Yes 1
Contairsment Bldg lower Conpartment
~
~
Normal Range Particulate 1-RE-90-106 A B
IE I
TRN A Yes Yes 5,9,10 Noble Gas 1-RE-90-106B B
IE I
1RN A Yes Yes 5,9,10 Iodine 1 -RE-90-106 C B
IE I
TRN A Yes No 5,9 Accident Range 1-RE-40-273/274 NA lE I
11N A/IEN B Yes Yes 1
Outside Contaitument Buildirs Personnel Hatch 1-RE-90-2 NA None Note 11 None No No 1
V.
Area Monitors Mein Control Room 0-RE-90-135 NA kne I
None b
No 1
Post Accident Sample Room 1-RE-90-280 NA Hone Note 11 None No No 1
i l
E86188.01 ^.
.O l
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 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 e
1080d - 01/08/87
Y
$NUFFS TABLE 11.5-3 LIQUID PROCESS RADICACTIVITT Mohlfons Sample Control-Alert Hi Flow Monitor Monitor Type Benge POC (1) ling Alarm Alers Bete Control Num jbo Description icontinuous) Detection (pCa/ec)
(yci/ce) tootope (pri/ce)
(pC4/ce)
( qpe ).,F_unctg 0-EG-RE-9 Ceeponent Liquid Met (TI) 10*' to 10"'
Ie 10**
Co-137 1 a 10**(3) 1 a 10**(4) 1-5 Isoletoe 0-EC-RE-10 cooling g ammme air wants water scantille-on component monitor tion cooling water surge tanks on Mi eterne 0-5J-RE-2 steen gener.
Liquid (2) met (71) 10*' to 10-n 1 a 10**
Co-137 1 a 10*8(3) 1 a 10**(4) 1-5 Closee stor liquid gesume blowdown radioactiv-scintille-toelation ity monitor tion valves on Mi ejere 0-DM-RE-25 Steam gener.
Liquid (2)
Net (TI) 10*' to 10*8 1 a 10-e Co-237 1 a lo s(3) I a 10**(4) 1-5 Closes ator blowdown gamme blowdown processing scintille-isolation erstem monitor tion valve on Mi storme 0-EA-RE-4A Service water Liquid Mel (TI) 30*' to IO*'
I a 10**
Co-137 1 a 10*883) 1 a 30**(4) 1-5 Alarme 0-EA-RE-43 monitor g esume scantille-taon 0-ME-RE-16 Doron recy.
Liquid (2)
Wel (71) 10*' to 30**
1 m Ip-e Co-137 1 a 10*8(5) 1 x 10**(6) 1-5 Alert eterm I cle system gesume diverto distillate scintille-flow to re-monitor tion cycle hold-up tant 0-5J-RE-01 Chemical and Liquid Met (TI) 10** to 1 NA 10*'(7) 1 (0)
.2-1 Alarme volume con-gesmos trol system scintille-letdown tion monitor 0-EF-RE-35 Essential ser-Liquid Mel (71) 10*' to 10*'
I a 10-e, c,.137 1 a 30-8(3) 1 a 10**(4) 1-5 Alerne 0-EF-RE-36 vice water gamme system monitor scintille-tion 0-FB-RE-50 Ammilier?
Liquid (2)
Net (TI) 10*' to 10-s 1 a 10-e Co-137 1 a 10*8(3) 1 a 10**(4) 1-5 Mi eterm steem erstem gesume isolates condeneste scintitle-availiery recovery tion eteem monitor supply to redweste building and tripe sueltiery steem con-deneste trenster pumpe new. 15 6/04
SNUFF $
TAmtX II.5-l (Sheet 2) t.80VID FROCESS RADI0 ACTIVITY MONITORS semple Control-Alert Mi Flem sesnitor Manitor Type 94nge POC (Il Igng Alarm Alare Date Control
{Contanuove,) Detectten (pC3/CCI (pCi/CC) ly top _e
{pC3/cc)
{pC3/CC)
{ go)
Function Nuatb]e Desegjpt,3On t
o 0-MC-RE-l Radweste so.
Ligued Nel (Til O.1 - 30'rshr 0.1 t/hr NA NA NA 18 4 88 4 0-HC-eF.-2 3adaiscatsen gaessa ayatem erentalle-monator tson (1) FOC - minimum detectable concentration.
- 12) when an operation.
135 One orden of magnitude above egic to avoid spurious alarms and to indacate tt e leakage of radioactivity into en otherwene nonredioacteve system.
(4) Two orders of magnit ude above MDc to andscote significant inleakage of radioactivity.
($1 only water cleaner than this well be sent to the reactor makeup water storage tent.
- 86) Magh actevity may endicate evaporator operating problem.
(7) Magh act avsty may andscate a crud t>uset or sodine opskang.
(8), High actavsty may andacate a cred burst, todane optkang, or failed fuel. 1.aboratory enelyoes will be performed to determine cause.
~
mev. I 9/80
\\
D
~
SNUPPS TABLE 11.5-2 LIQUID EFFLUENT RADIOACTIVITY MONITORS Sample Control-Alert Hi Flow Monitor Moniter Type Ran9e MDC (1) ling Alarm Alarm Rate Control Number Description (continuous) Detection (pC1/cc)
(pCi/cc) Isotope (pCi/cc)
. (pCi/cc)
(qpm)
Function 0-HF-RE-45 Secondary Liquid (4)
Mal (TI) 10 ' to 10~8 1 x 10**
Cs-137 (3)
(2) 1-5 Closes
~
liquid waste gamma discharge system scintilla-valves on monitor tion high alarm 0-BB-RE-18 Liquid rad-Liquid (4)
Mal (TI) 10 to 10~8 1 x 10
Cs-137 (3)
(2) 1-5 Closes waste dis-gamma discharge charge scintilla-valve on monitor tion high alarm 0-LE-RE-59 Turbine Liquid (5)
Na! (71) 10 ' to 10~8 1 x 10
Cs-137 (3)
(2) 1-5 Closes building gamma discharge drain
~
scintilla-valve on monitor tion high alarm 0-BM-RE-52 Steam gener-Liquid (4)
NaI (TI) 10~' to 10~8 1 x 10
Cs-137 (3)
(2) 1-5 Closes dis-ator blow-gamma charge and down discharge scintilla-blowdown monitor tion isolation valves on high alarm (1) MDC = minimum detectable concentration.
(2) High alarm is set to ensure that Technical Specification limits (the 10 CFR 20 l
general population MPCs for the controlling isotope at the boundary of the restricted area) are not exceeded and to initiate isolation before the limit can be exceeded.
(3) Alert alarm is set one order of magnitude below the Technical Specification limits to alert operators of alert radioactivity levels.
(4) Normally, all of this liquid will be recycled. The monitor is to prevent inadvertent discharge valve openin9 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.
Rev. I 9/80
\\
I SWue..
TABLE 11.5-3 AIRBORNE PROCESS RADIOACTIVITY MON! TORS Total Minimum Control-Alert Hi Venti-Seguired Monitor Type Range MDC (1) ling Alarm Alarm lation Sonettivity Control Monitor (contanuous)
(pC1/cc}
(pCi/ccl Isotope (pci/cc)
(pC1/ce)
Flow (cfm)
(pCi/cc)
Function 0-CT-RE-31 Particulate (3) 10*8' to 1G*'
I a 10 88 Co-137 1 a 10**(8) 1 a 20*'(7) 420.000 1 a 10*'(7) leolates con-0-C7-RE-32 teinment purge, Containment Iodine (4) 10*88 to IO*'
1 a 10*8' I-138 9 a 10**(8) 9 a 10*e(7) 420.000 9 a 10**(7) de-energises atmosphere purgo Iene on monitore casoone (3) 10*' to IO*'
2 a 10*'
Er-85 1a 10**(8) 1 a 10**(7) 420.000 1 a 10**(7) high gaseous activity via the ESFAS (see Section 7.3 ).
0-CT-RE-22 Particulate (3) 10 se to 10*'
I a 10*88 Co-137 1 a 10**(8) 1 a 10*'(7) 20.000/4000 1 a 10*'(7)
Isolates con-l 0-CT-RE 33 taimment purge,l Containment Iodine (4) 10 as to IO*e 1 a 10*88 I-131 9 x 10**(8) 9 a 10**(7) 20.000/4000 9 a 10*8(7) de-ener?ises purge system purge fans on monators Caseous (3) 10*' to 10*8 2 a 10*'
Kr-85 1 a 10**(8) 1 a 10**(7) 20.000/4000 1 a 10**(7) high 9aseous activaty via the ESFAS tooo Section 7.3) 0-CT-RE-59 Camma (5)
I to 10' rede 1 red NA NA NA NA NA NA O-CT-RE-60 V
- M Containment h&gh activity mona tore O-CE-RE-92 Caeoous 10*' to 10*8 2 m 10*'
Kr-85 2 a 10**(9) 2 a 10**(10) 1000 NA Clooes blow.
Condenser (continuous) down toolation air dio-(3), (6) valve on charge ni alarme monitor Particulate (lab analysis) (6)
Iodine (lab analyste) (6) 0-OG-RE-27 Particulate (3) 10*88 to 10*'
I a 10*88 Co-137 1 a 10**(8) 1 a 10*'(7) 20.000 1 a 20*'(7)
Inittetoe 0-OC-RE-20 avitch to fuel Fuel build-Iodine (4) 10 sa to 10**
1 a 10*8' 1-131 9 a 10**(8) 9 a 10'e(7) 20.000 9 a 10*8(7) building ing exhaust emergency ven-monitore caseous (3) 10*' to 10*8 2 a 10*'
Kr-85 1 a 10**(8) 1 a 10**(7) 20.000 1 a 10**(7) tilation on gyy high gaseous activity via the ESFAS (see section 7.3) 0-CE-RE-04 Particulate (3) 10 se to 10*'
Ia 10*88 Co-137 1 a 10 e(8) I a 10*'(7) 1950 1 a 10*'(7)
Initiatee 0-CR-RE-05 evitch to con-Control lodine (4) 10*sa to 10**
1 a 10*8' I-131 9 a 10 '(8) 9 a 10**(7) 1950 9 a 10**(7) trol room room ear emergency ven-ourply caseous (3) 10*' to 10*'
2 a 10*'
Kr-85 1a 10**(8) 1 a 10**(7) 1950 1 a 10** ( 7 ) tilation on monitors high gaseous activity via the ESFAS (see Section 7.3) sample flow for each channel is 3 cfm (I) MDC = minimum detectable concentration.
(2) when fuel na an the buniding.
(3) Beta scintillation detector.
(4) Camme scantallation detector.
(5) Comme sensatave non chamber.
(6) when in operetson.
(7) 10 MFC.
(R)
M'C (91 Dne order of magnitude above MDC to avoid spurious alarme and to indicate primary to secondary leakage.
(10) Two ordere of magnitude above MDC to indicate engnificant anteekage of radaoactivity.
,,,[
- S/02
J
+-
.,r~
SterrPS TABt.E II.5-4 AIPPORNE EFFIEENT RArntOACTIVITY MONITOR $
Tntal Minimum control-Alest Hs Venti-Dilm-pequired Monitor Type penge MDC fll line Alarm Alerm lation tion senettivity Control Monitor
[continuouM (pCl/ce)
(p_C /cel isotog kCa/ce], kC ag F_l o_wteful Factor tyCi/cci Function 0-CT-SE-21A Partneulate (2) 10" to 10
I a 10*'8 re-I t? -
(R)
(71 66,000 t4l 85)
Alarne riant unit vent Iodine (3) 10* to 10'*
Ia 10"
l-13I tel (7) 66.000 (4)
(5) (6) monator 0-CT-RE-219 Caseous (2) 10*' to 30' 2x 10
Re-133 (8)
(7) 66,000 (4)
(5)
Plant unat vent monator O CH-RE-10A Particulate (2) 108 to 30*'
Ia 10*se Cs-137 (8)
(7) 12,000 (4)
IS)
Mi alors teolates the madweste buildang todane (3) 10* to 10
- 1a 30
l-131 tel 17) 12,000 (4) 15) weste gae decoy tank discharge exhaust line moetator O-CH-RE-109 Caseous (2) 10*' to 10' 2a 10
Ne-133 (8)
(7) 12.000 (4)
(5)
Pedweste bualding enhevet monitor 0-CL-RE-60 Ausstaary Particulate (3) 10 " to 10~' 1a 10*
Co-137 (8)
(7) 20,000 te)
(7)
Aleres ventitetson exhaust monator 0-CN-RE-41 Access Particulate (3) 10*'8 to IO*'
Ia 10*
Cs-137 881 (7) 1950 (4)
(7)
Alarme control area ventilotson exhaust monster
%mple flow for each channel as 3 cfm (1) fec e minimum detectable concentration.
(21 Mete scantalletson detector.
(3) Cassna scintallatson detectos.
g rate in m /sec g tannual average).
3 (4) Dalution factor e vent flow
- 85) Minamum required senettivity of monitor in pCi/cc at manimum allowable annual average concentration of controllang asotope at monitor which wall sesult in annual average Appendia I dose at the ette boundary a population MPC for controllsng l
I I
where the bioaccumulation factor is I for teotope ' T63 "
bioaccumulation factor " dalution factor g
noble gases and 1,000 for todines and particulates. See Offsite Dose Calculation Manual.
(6) Crab samples wn!! be analyred in the laboratory, and low todane concentrations wn!! be calculated, usang paeviovely established ration.
(7) High alarm se set to ensure that technical specifacetton linjte (the 10 CFD 20 general population MPCs for the controlling tsotopes at the boundasy of the restricted areal are not enceeded.
- 18) Alert alarm to set to alert operators to that average concentration which, af ma6ntelped for a full year, would result an the 10 CFR 50 Appendia I annual dos
- guadelance being reached.
See offente Dme Calculation Manual.
O O
^
.e..
5/02
1 d.
SNUPPS TABLE 12.3-2 AREA RADIATION MDNITORS Instrument Radiation Range ill Alarm Hi-H1 Alarm Number Locatinn Zone (mrem /hr) tarem/hrI terem/hrI 0.1 - 10*
2.5 (Il 15 (2)
O-SD-RE-1 Radweste Butiding Corridor, Basement B
0-SD-RE-2 Radweste Bullling Corridor, pasament B
0.1 - 10 2.5 (1) 15 (2) 4 L.SD-RE-3 Radweste Building Corridor, Ragement D
0.I - 10 2.5 (1) 15 (2) 0-SD-RE-4 Radweste pullding Corridor, Ground Floor R
0.1 - 10, 2.5 (1) 15 (21 0.4 - 10, 2.5 Ell 15 (2) 0 SD-RE-5 Radweste Building Corridor, Ground Floor B
0-SD-RE-6 Solid Redwaste Area B
0.1 - I n,,
2.5 (1) 15 (2)
B 0.1 - 10 2.5 til 15 (2) 0-SD-RE-7 Truck Space 0.1 - 10,4 2.5 (1) 15 (2) 0-SD-RE-8 Sample Laboratory B
0-SD-RE-9 RW Bldg Valve Room Corridor C
0.1 - 10 15 til 100 (2) 4 0-SD-RE-10 RW Bldg Valve Room Corridor C
0.1 - 10 15 (11 100 (2) 4 0-SD-RE-11 RW Bldg HVAC Filter Unit B
0.1 - 10 2d W 15 W 4
- 10 2.5 (Il 15 (2' 0-SD-RE 12 Aus Bldg Corridor Rasement B
0.1 0.1 - 10,4 2.5 til 15 (2)
O-SD-R E-13 Aun Bldg Corridor Basement B
0-SD-RE-14 Aus Bldg Corridor Basement B
0.1 - 10, 2.5 (18 15 (2) 0-SD-RE-15 Aus Bldg corridor Basement n
0.1 - 10 2.5 (1) 15 (2) 4 0-SD-RE-16 Aux B1dg Corridor Basement B
0.1 - 10 2.5 (1) 15 (21 4
0-SD-RE-17 Pipe Tunnel 6 Personnel Access B
0.1 - 10 2.5 W 15 W 4
0-SD-RE-18 Aus Bldg Ground Floor Corridor 5
0.1 - 10, 2.5 (Il 15 (2) 0-SD-RE-19 Aus Bldg Grourid Floor corridor B
0.1 - 10 2.5 (1) 15 (21 0.1 - 10,4 15 (1) 100 (2)
~
0-SD-RE-20 h Bldg valve Room Corridor Ground Floor C
0-SD-RE 21 ablR 91dg valve Room Corridor Ground Floor C
0.1 - 10, 15 (1) 100 (2) 4169 Corridor Ground Floor 5
0.1 - 10 2.5 W 15 W 0-SD-RE-22 4
0-SD-RE-23 A-
"s4g Corridor Ground Floor B
0.1 - 10 2.5 W 15 W 4
0-SD-RE-24
- " 4 era e Room C
0.1 - 10, 15 (1) 100 (2) 4t?st ott Aus Bldg A
0.1 - 10 0.5 (1) 2.5 (2) 0-SD-RE-25 se&* Enchanger Outende B
0.1 - 10, 2.5 (1) 15 (2) 4 0-SD-RE-26
. ca Filter Unit C
0.1 - 10, 15 (1) 100 (2) 0-SD-RE-27
-. Personnel Hatch B
0.1 - 10 2.5 W M W 0-SD-RE-28 4
0-SD-RE-29 Hot Machthe Shop B
0.1 - 10, 2.5 til 15 (2) 0-SD-RE-30 Hot Instrument Shop B
0.1 - 10 2.5 (Il 15 (21 4
0-SD-RE-31 Hot Laboratory B
0.1 - 10 2.5 (1) 15 (2) 4 0-SD-RE-32 Control Bldg Cortjdor B
0.1 - 10, 2.5 (1) 15 (2) 0-SD-RE-33 Control. Room A
0.1 - 10, 0.5 (1) 2.5 (2) 0-SD-RE-34 Cask Handling Area (3)
B 0.1 - 10 2.5 W 15 W 4
0-SD-RE-35 New Fuel Storage Area (3)
R 0.1 - 10 2.5 (1) 15 W 4
0-SD-RE-36 New Fuel Storage Area (3)
D 0.1 - 10 2.5 (1) 15 (2) 4 0-SD-RE-37 Spent Fuel Pool Area (3)
B O.1 - 10 2.5 W 15 (2) 4 0-SD-RE-30 Spent Fuel Pool Area (3)
B O.1 - 10 2.5 H) 15 W 4
0-SD-RE-39 Seal Table Area E
0.1 - 10 1000 M )
100M W 4
0-SD-RE-40 Personnel Access Hatch Area E
0.1 - lo 1000 (4) 10000 (5) g 0-SD-RE-41 Containment Building E
0.1 - 10, 1000 (4) 10000 (5) 0-SD-RE-42 containment Building C
0.1 - 10 1000 (4) 20000 (5) 0-SD-RE-43 Technical Support Center A
n.1 - 104 0.5 til 2.5 (21 O-SD-RE-44 F.mergency Offnite Facility A
n.1 - 104 0.5 Ell 2.5 (2) g In-10) 1000 t4l 10000 til 0-SD-RE-47 Pass Sampling Room Portable manipulator Bradge Crane (61 1.0 - 10 (71 N/A til Hich alarm set for maximum radiation level for the rad!ation zone for that area.
(2) High-high alarm set for the maximum radiation level for the radiation zone above the one for that area.
(1) These monitore serve as criticality monitors.
(4) High alarm based on highest espected radiation level for the area during full power operation.
(5) Hinh-high alarm set one order of magnitude above high alarm to indicate extremely high radiation level.
(6) This is a portable monitor providenq a local alarm and readnut. The mnnitnr w!Il be positioned on the bridge crane only during plant shutdnwn when fuel handling activities are necurrino. This monitor will p,y gg be replaced,by a permanent mon i t os which will be installed at Callaway dursnq the first refueling nutage.
6/94 178 High alarm an establenhed for the g.rnt ect ion of ogwr at or s. on the bandua crane and th set at 1% mrem /hr above background radsation Icvelg, s
TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 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 t
1080d - 01/08/87
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TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (B)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 35 0F 36 ATTACINENT NO. 7 San Onofre 2 & 3 FSAR a.
Table 11.5-1 Continuous Process and Effluent Radiation Monitoring b.
Table 12.3-2 Area Radiation Monitor Locations t
j
[
1080d - 01/08/87
e of e
Table 11.5-1 CONTINUOUS PROCESS AND EFFIEENT RADIATION MONITORING (Sheet 1)
E.rece44 41.
It) e,.....,
- t. i ii. e.
e..e.
C - e........
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f e.. i, > i r,
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.s ur.as 6.0 i.e t,-.t e t i -
al... e.d :=ces.te f7/181.FR56; Er 85 et hee ela..re af weste noe fie..e 88.3. )
p eelefille.
dt.ch. fee v.lve flan mesteell,atten 7
offllmel
,egentgtle.
C,.e, e re.317 i n**. t p* I
- 2. 4e l ft-O Se10**
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.==P discherse il per lig.Id tian fatDI st =ttee entti til (FeT 713 7 and leT.7917 fle.
D are In.6 7 e i, f e t 0** '*
Iae t ri e=t o t ien Aleto saly f_
It 2
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'3" CI e.
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fuel.
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MM t.
A,twel ala,e oefenfaf. e.t.3.lf*h*d h. th* **e%mirel 'Periffrettens.
Table 11 5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION MONITORING (Sheet 2) f.pected nie li)
Aoiseets, Actie..
(sts/r=y)
C re...p) e seipei.g
.r.6..
Ceiise.t t-es e fpCd/r=
spC6/v= 1 Pe=et Sepply lattisted se.,ieri.togner la<etsaa Oseatsty Se=Pler Type Detectar Type M-e==eed leasare 5.%el0
Instrumentotten Alero end Alvert
- I pedweste i
Offl6me/
y sciat elle-Groes y Co-837 IS' -10 IJtD Co 337 oc bee flew to esorel-rendensete 109 64 tien laneses eastes veterm (BCR) tant enester 2/1RT-7812 feauve 30.2-3 sh Il Er-85(8I 10
-10'I 5eloIe-833 Is30'I Vitel oc buses Alere and tattlete
-6 C==e e s ament 6
Ces 9 ocentBIIe-Crees it teatet y. g perse Re-113 se*harme (fA)
(2 per,
tien
...i. tie I#3
- 6ter m.tt
-9
-4
-9
-9 op 1ai-ta06-1, sta*tas p ociatille-Crees P Cl-36 &
80
-10 3.9s30 Belo Vital oc beoes Alere end lettlete (2p7-7a06 5, U
2eT-IS07-2, pepe r, tien
$r*90 Co-537 Co-437 rentet
)perge feeletfea q) p and 187-7807-2; perticulate (opere 9 6-2 fliter Fteed y ectetelle-Crees y/
Be-133 10
-80' 2.3s10 I-831 Set 0
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.e
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2:
sh Il Offilme/
{t ettettile.
Casse P Cl-36 &
10
-ID' l.MD/lje et hoe closure of the easte y
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- E me*6aa O
repee per-g,y 16 rel at e 868ter Alere and laittate v t"*
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y eclet6lle.
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Re-113 IO
-80' 6,%s30
l. 3sy' /
Ins.t rument e t t en o si
.. sere se i - -este
- v. i-nl 2.i0
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essed thennel 7
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1
e v
e Taile 11.5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION MON 1 TORI!;G (Sheet 3)
Espected Alere (Il Aetemette Artiene Sempler,ma g er Art s et t y Celebretten Sease Cancentregtene Setreing y.
. C4,r. )
re.er se,,i, iettisted 7,,. I m.t.
.etit, s - ier v,,e Oete t.r tr,e
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. 0.s,0
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.-in Co-In too.neet t.o.
u n.1 -1 0,.
Jale iflgere 9 6-9 f6eed g
i.iii
..eet 28
,e.tt. ete filter end (b.treal cartridge Offilme/ges 9 ociatille-Groes 9 Br-05 10' -80'I N
6ste
- vital oc buses Alere med ta,ltiete,.el
. Feel hendtles J n 4 ie.let.
e m hendtlag Lees from m,
er... t,~
r o.a.ier tt e
strberse settl the normel-sectilo-g3 monster ties eyeten end O
(2RT-Fe22-1 ert eet tee of t h, 157-F522-3, feel headling eres co 2RT-7823-2 entdent cleener
- ts e%
Q. *t 3RT-7823-2; most
~t n
fagere 9 6-9 3
J l
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y octettile-Groes y Co-137{,y 10,-10.
N 2ste,
vital oc beoes Alere eed lettlete r3 p Q. EM toelattee of the g
W teetimettet ties Ba-133 Co-13f/
2x10' g feel be.ditos stee 9
flued I-131 free the mereal y
e,9 portacolate veettlettee eyotes 2o m
filter oed e.d.et..t.
.f On g
5g
..,.r eei of the fee
..rt..d.e hendtlag eres sect-9 gn dent eleeoup east OW 30'0-10 IJtD 2 e 10' Vital oc beses Alero end inattete
- I Centrol reeen 2
Offitoe/ges 9 ottatille-Grose p Er-05 gr-85 teetet ten of the o
etrboree teen neraal ee. trol goes tel
.montier ocetstate n systee Q
(2f)ti-7826 1 end acteetten of p
2/387-7025-2; the emersemey g
g, flsere 9.4-0
.ie..e,e,etre
~. t n l
Offitnef y ectattilo-Creso y Co-137/
10-10' l>tD 2 10
Vital et buseo Alere sad taltiete
-o t*
teelet ten of the g
I seettnetic/
tese Be-833 Co-l){/
Jet 0*
mereel t*atrol y
II.ed ys I-831 fee. *entitetten ow 1
perticulate systee and actos-O filter end mg tt
.f t e
..ree.i e.ergene, e teenop gg restridge fl
-a.
~
- ~ ~ - - -
~
2 :o.
tn t~
e
e Table 11.5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION MONITORING (Sheet 4)
Forerted Alern(13 s., i.. ig.,
a......,
r.iih...
soose r
- e..egi-.e sei e....g nei terarti e i...
o
...t,
- s.,ier 7,,e n,. e,.. Tm a.....e l....re s <.e..,I sieur. I a c ir-p r.-Pr se,,i, i.iisated fa.de. nee e6e 2
offt.ne/see Law remee:
Crees p tv-R%
IO' -10'I 6.3%sIO' 9 sin' Ins t rument at ion Alere only ejectee see (I per p eeint.Ile-Re-833 oc bee IC AD Cl
==6 e )
t.
g maattee 17s7-7a10 and Nigh range:
Creen P tr-R%
10-102 IJWt 2s10' Instr.usentetten Alere only 187-7810; P ersetelle-Ee-133 oc bee f.e re 9.6-9 teen eh 2)
Cee.deaser ett 2
Offline/see Law reare-Crase y Cl-17 10 to 4.1% ele' 9eIO' Vital oc beoes Alero sely electas wlee (I per
- pleet$r le Re-133 g,y rease manitet onst erlatilleter (Re-333) 12s7-7579-5 m.
,g a
==d 1st-7470-5 feed-rease:
crees y Co-837 10 to De Vital se boses El 2
tie.ee 9.6-9 e lid stete to o
eh 21 (Ie-133) g w
CO
'U es.
iO;'t.
- t. ;;
... re.ee:
cree.,
Co-n, ue vitei ec w ee
.ei.e egete iO CD (Ie-813) 4 Mb ntfIseef no deterter og 6easemetoc/
Ap
- ef
- f. seat per-2O M
eeenlete g,g f.l.ee w (n H En O
netgeoe/.,,
hb
'e deterter W
ze
. e.e. -t f4med o6I.er O g seesete q
e art e es.se
- wj t*
En>=
2H T
t"*
w W.
OwO tn t*
- < O En O H==
tv1 n 3
tn
s e
Table !!.5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION MONITORING (Sheet 5)
Espected gy Se.ple,fn.g.,
ac t e es t y ce 66,eten.
Retae Cemeentreg6ees Retrolet Aetemellt Attlene B. arete==
Oueettty Sampler Type Deteeter Type nesseted lentare (sac e / reg)
(pCe/e= I (pCerrey)
Power Supply intiteted
~. _._
<-t e s-.t 2
onei..ei.ee tes.
.e, c,oes,
Ci-37
..-' to s 6.in 'i
.s io,'
Viisi e, seee
.is.e.,4.mi..eie
,w. e.-
ei,e,
,ieet.,
i..
uin...>
.iesure.. sosie rient seat onst sciatellster (Re-833) see discher e s t ee t on de
- solo, rease Mid-rompe:
Green y Co-937 IO, to LMD Vital er buses fe=Itchehle, sette state In Jef.7aa5 3 and (ge.133) 197 7M %-I fleste V.4-2.
==-
S sh 2)
Wegb range:
Crees y Co-137 BC to l>W Vital oc beses solid state in (Xe-833) se detector th Offlinet a as
. so...t a
fleed per-t.ei.te g
filter 1
w co 7
g%
Offlinet se detector fy (A
teettnetic/
g.,
fleed elleer it to ecellte Q. O terteldee W
9 e
2 M
n.ile ete==
4 Aree redle-Les reaget Crees y Co-lit 10.
to IJO l.0s30 Vital oc beses Alere
- g o tn 4
llae enet tae (2 per tien menetse De tub, IO et/h ar/hr Q
(,97-787549 watt)
Be-831 68 th 2eT-787&Al.
HM
.g IJe I. Oslo, Vital beoes Alere O
2ef-7A7554, 4
Atee redle.
Righ range:
Crees y Co-337 10i.6,t o 2e,.
7.si.
(2,e, t.
ee.. t e,
...t iar rime 5
lef. 7 9 FS A $.
unit) thamber Ie*III g
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Table 11.5-1 CONTINUOUS PROCESS AND EFFLUENT RADIATION MONITORING (Sheet 6 of 6)
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k Srn Onsfra 2&3 FSAR Updated RADIATION PROTECTION DESIGN FEATURES Table 12.3-2 AREA RADIATION HONITOR LOCATIONS (Sheet 1)
Elevation Ala rm(b)
I I*
Setpoints Quantity Building (ft)
(in.)
Location (area /h) 1 Auxiliary 9
0 General area 2.5 (radwaste) 1 Auxilia ry 24 0
Local sample lab 2.5 1
Auxilia ry 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)
Normal operation 6.5 Refueling 2.5 operation 2
Safety B
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 Auxilia ry 70 0
Radiochem lab 2.5 1
Auxiliary 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 a.
Total number of detectors for Units 2 and 3.
b.
Alarm setpoints are based on calculated gamma dose rates. Ala rm setpoints may be reset based on measured radiation levels.
12.3-33
r t
S:3 Onofre 2&3 FSAR Updated RADIATION PROTECTION DESIGN TEATURES Table 12.3-2 AREA RADIATION NONITOR LOCATIONS (Sheet 2 of 2) g Elevation Alarm ( }
Quantity (*
Building (ft)
(in.)
Location (area /h)
Setpoints 4
Containment 63 6
General area -
safety-related (2 per unit)
Normal operation 625 Refueling 2.5 operation 2
Containment 93 0
High-range 10,000/
in-containment 100,000 l
monitors -
safety-related (1 per unit)
Dual setpoints 2
Containment 98 0
High-range 10,000/
in-containment 100,000 monitors -
safety-related (1 per unit)
)
Dual setpoints i
I l
f 12.3-34
8 TVA EMPLOYEE CONCERNS REPORT NUMBER: 229.11 (8)
SPECIAL PROGRAM REVISION NUMBER: 2 PAGE 36 0F 36 CATD LIST s
The following CATDs identify and provide corrective actions for the findings included in this report:
229.11(B) SQN 01 (01/06/87) 229.11(8) SQN 02 (01/06/87) t 1
j I
1080d - 01/08/87
{
~
g 9
1 1
REFERENCE
- ECPS128J-ECPS121C TENNESSEE VALLEY AUTHORITY
.PAGE 119 FREGUENCY
- RECUEST OFFICE OF NUCLEAR PDHER RUM TIME - 12:57:19 4
CNP - ISSS - RHM EMPLOYEE CONCERN PROGRAM SYSTEM CECPS)
RUN DATE - 12/02/86 q
LIST OF EMPLOYEE CONCERN INFORMATION CATEGORY: EN DES PROCESS & OUTPUT SUBCATEGORY: 22911 PROCESS RADIATION MONITORING ADEQUACY S
GENERIC KEYNORD A E3 H
APPL QTC/MSRS P
KEYNORD E CONCERN SUB R PLT EBSH INVESTIGATION CONCERN KEYMORD C NUMBER CAT CAT D LOC FL0B REPORT R
DESCRIPTION KEYNORD D
)
j 10 144-001 EN 22911 N H5N NNYY SR CI DOES NOT FEEL THERE IS ENOUGH RAD DESIGN PROCESS T50115 K-FORM IATION DETECTION EQUIPMENT IN THE PL STANDARDS
)
ANT: SPECIFICALLY, ON THE RADIDACTIV ENGINEERING i
i E PROCESS PIPING SYSTEMS (CI DID NOT RADIATION PROTCTN 9J j
SPECIFY SYSTEM 9'S) IN UNIT I AND I I
N THE SHIELD BUILDING VENT STACK FOR
)
UNIT 1.
CI FEELS UNIT 1 SHIELD BUI I
LDING VENT STACK NEEDS MORE RADIATIO SI N MONITORING EQUIPMENT TO MEET FEDER AL GUIDELINES. CONSTRUCTION DEPARTM ENT CONCERN. CI HAS NO FURTHER INFO RMATION. NO FOLLON UP REQUIRED.
-O 1 CONCERNS FOR CATEGORY EN SUBCATEGORY 22911 9
.O 1
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