ML18026A962
| ML18026A962 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/30/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097, RTR-REGGD-1.97 GL-82-33, NUDOCS 8405080128 | |
| Download: ML18026A962 (228) | |
Text
HBGULATORY IIVFVHlYIATIOIV 0ISTRIUUT ION SYSTEM (KIDS)
ACCESS ION IVdl<: 6405080128 DOC DATF: 84/04/30
~ NO ARIZEi): YES I DOCKET FAC IL 50 259 drowns Ferry Nuclear Power Stationi Unit lP Tennessee 08000259 50"260 OrOwnS Ferry NuClear POWer StatiOnP Unit 2E TenneSSee 50 ss29e 6rowns Ferry IvucIear Po~er Stations Unit 38 Tennessee 05000296 Au TH. IIANE, Au T IIOR AF F IL 1 A T ION fYIILLSPL~ m. Tennessee Valley Authority HEG IP. NA'>E HEGIPIENT AFFILIATION DEilTON<H office of Ivuclear Reactor HegulationP Director SUUJECT: Forwards detailed evaluat.ion of Req Guide 1.97 requirements imolementation planssper request in 8?1217 Generic Ltr h 88-33 re e ercecnY resccnse facilities.
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I VAot 000 Chestnut Street Tower II April 30, 1980 Mr. Harold R. Denton, Director Office. of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
In the Matter of the Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 A detailed evaluation of Regulatory Guide 1.97 requirements and implementation plans for the Browns Ferry Nuclear Plant is enclosed.
This submittal is made in response to the request made in Generic Letter 82-33 dated December 17, 1982.
If you have any questions, please get in touch with us through the Browns Ferry Project Manager.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. . Mills, M nager Nuclear Licensing Subscribe/
me this ~~~ sworn to da of efore 1984.
Notary Public My Commission Expires Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20814 8405080i28 840430 PDR ADOCK 05000259 F PDR IL
@OS'~ ~~
ENCLOSURE RESPONSE TO REGULATORY GUIDE. 1.97 FOR BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3
0 1.0 Discussion NUREG-0737, Supplement 1, Xtem 6, "Regulatory Guide (RG) 1.97-Application to Emergency Response Facilities," states that each operating license holder provide data to assist control room operators in preventing and mitigating the consequences of reactor accidents.
RG 1.97 provides guidance to ensure that instrumentation necessary to measure certain prescribed variables and systems during and after an accident is available to the appropriate personnel. The "BWR Position on NRC Regulatory Guide 1.97, Revision 2," was Owners'roup published July 1982. TVA participated in this BWR Owners'roup (BWROG) effort. ln Nay 1983, RG 1.97, revision was published and will be used to respond to item 6 of NUREG-0737, 3,supplement 1.
Although RG 1.97, revision 3,is being addressed by TVA, the BWROG position on revision 2 is applicable in many instances, and TVA endorses that position where applicable.
- 1. 1 RG 1.97 Classification of Variables 1.1.1 Variabl'e Types Five types of variables have been identified by RG 1.97 for the purpose of aiding in the selection of accident monitoring instrumentation and applicable criteria.
Classification as one type of variable does not preclude it from being designated as any other type.
1.1.1.1 Type A A type A variable provides prima y information needed to permit the control room operating personnel to take the specif1.ed manually-controlled actions for which no automatic control is provided and that is required for safety systems to accomplish their safety functions for design basis accident events.
1.1.1.2 Type B A type B variable provides information to indicate whether plant safety functions are being accomplished.
1-1.'1.3 Type C A type C variable provides information to indicate the potential for or the actual breach of the barriers to fission product release.
This includes the fuel cladding, primary coolant pressure boundary, and *the containment. I
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A type D variable provides information to indicate the operation of individual safety systems and other systems important 'to safety.
1.1.1.5 Type E A type E variable provides monitoring capability used in determining the magnitude of the release of radioactive materials and for continuously assessing such releases.
1.1.2 Category Regulatory positions 1.3 and 1.4 of RG 1.97 provide design and qualification criteria for the instrumentation used to indicate the various variables designated. The criteria are separated into three separate groups or categories depending upon their importance to safety.
1.1.2.1 Category 1 Category 1 provides the rmst stringent requirements and is intended for key variables.
In general, category 1 provides for full quali-fication, redundancy, and continuous real-time display,and requires onsite (standby) power. A key variable is that single variable that most directly indicates the accomplishment of a safety function.
1.1.2.2 Category 2 Category 2 provides less stringent requirements.
It does not include seismic qualification, redun-dancy, or continuous display and requires only a high-reliability power source (not necessarily standby power).
1.1.2.3 Category 3 Category 3 is intended to provide requirements that will ensure that high-quality off-the-shelf instrumentation is obtained and applies to backup and diagnostic instrumentation. It is also used where the state-of-the-art will not support requirements for higher-qualified instrumentation.
0 2.0 Desi n and Qualification Criteria for Browns Ferr Nuclear Plant The types A, B, and C variables serve a primary safety function. They are used by the operator to ensure (i) the capability to shut down the reactor and maintain it .Cn a safe shutdown condition, (ii) the integrity of the fission product boundaries, and (iii) the capability to mitigate the consequences of accidents which could result in potential offsite exposures comparable to the exposure guidelines of 10 CFR part 100. The type A variables are used for the required operator actions that are needed to give the design basis behavior for the design basis events (accidents). The types B and C var iables are used to monitor whether or not the events are following the design basis behavior and to indicate the need for major contingency actions if the event goes beyond the acceptable design basis behavior. Thus, in general, most of the instrumentation for the types A, B, and C variables need to be safety grade. Where instrumentation is used as a backup, the backup need not be safety grade, therefore, category 3.
The types D and E variables, in general, do not serve a primary safety function. They are not needed for ensuring design basis behavior or for major contingency actions. These variables only supply additional information by indicating system operating status, diverse variables, and low-level radiation releases.
The variables can be used to enhance safety by allowing the operator to improve the system operation over the minimum required for design basis behavior, determining what system has failed, etc. The types D and E variables are not essential, and the instrumentation does not need to be safety grade. At the present, no types D or E variables have been identified as category 2 in accordance with the above design basis; two type D variables have been identified as category 1.
. Therefore, in the opinion of TVA, there are only two design and qualification criteria, i.e., categories 1 and 3. These two categories meet the intent of RG 1.97 in that all primary information supplied by key variables (types A, B, and C) will meet the intent of category 1. Backup (types A, B, and C), diagnostic, supplemental, and confirmatory information (types D and E) will meet the intent of category 3.
The primary differences between the category requirements are in qualification, application of single failure criteria, power supply, and display requirements. Category 1 instrumentation requires seismic and environmental qualification, the application of single failure criteria, standby power supply, and display requirements. Category 3 instrumentation does not require single failure criteria or an immediate accessible display and does not always require emergency standby power. We believe this meets the intent of the regulatory guide.
~O 0
2.1 Design Criteria for Categories 1 and 3 Instrumentation All categories 1 and 3 instrumentation shall meet the following criteria except where specified in the individual instrument description in attachment A.
Equipment Qualification 2.1.1.1 Category 1 Category 1 instrumentation will be qualified in accordance with the methodology described in IE Bulletin 79-01B. Instrumentation whose ranges are required to extend beyond those ranges calculated in the most severe design basis accident event for a given variable will be qualified using the guidance provided in paragraph 6.3.6 of ANS-4.5, in that: "No additional qualification margin needs to be added to the extended range variable. All environmental envelopes except that pertaining to the variable measured by the information display channel shall be those associated with the design basis accident events."
Continuous indication of redundant instrument channels will be provided. Qualification applies to the complete instrumentation channel from sensor to display where the display is a direct-indicating meter or recording device.
The redundant channel need not necessarily be displayed on a qualified display device, but the channel must be fully qualified from the sensor to a location which is accessible to the unit operator during accident conditions.
The seismic portion of the qualif1.cation of existing equipment is in accordance with the requirements established at the time of installation. Any new equipment will be qualified in accordance with Regulatory Guide 1.100, "Seismic Qualification of Electric Equipment for'uclear Power Plants."
Category 3 The. instrumentation will be at least high quality commercial-grade equipment.
II 2.1.2 Redundancy 2.1.2.1 Category 1 Category 1 instrumentation will be redundant in that no single failure within the accident-monitoring instrumentation, its auxiliary supporting features, or its power sources concurrent with the failures that are a condition or a result of a specific accident will prevent the operators from being presented the monitored variable in an unambiguous manner.
Specifically for category 1 instruments, if a failure of one accident-monitoring channel results in ambiguous information that would lead operator s to defeat or fail to accomplish a required safety function, one of the following measures will be provided:
(i) Cross-checking with an independent channel that monitors a different variable bearing a. known relationship to the variable being monitored.
(ii) The capability of perturbing the measured variable to determine which channel has failed by observing the response on each instrument.
(iii) The use of portable instrumentation for validation.
(iv) A third channel of instrumentation..
2.1.2.2 Category 3 No specific provision is made for providing redundant instrumentation for category 3 variables.
2.1.3 Power Source Category
'.1.3.1 1
Category 1 variables will be powered from station standby power sources. Power sources are individually identified in attachment A.
0 2.1.3.2 Category 3 category 3 instrumentation will be powered from highly reliable power sources but'"not necessarily standby power. Attachment A l'ists the power supply for each variable.
2.1.4 Channel Availability 2.1.4. 1 Category 1 The instrument channel will be available,prior to an accident except as provided in IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Station,. paragraph 4. 11;,
'Exceptions',"'r as specified in the technical specifications.
- 2. 1.4.2 Category 3 No specific provision provided.
- 2. 1.5 Quality Assurance 2.1.5.1 Category 1 Quality assurance for category 1 variables will be consistent, with the Browns Ferry Nuclear Plant (BFN) FSAR.
2'1.5+2 Category 3 Quality assurance for category 3 variables will be consistent with the, BFN FSAR.
2.1.6 Display and Recording 2.1.6.1 Category 1 Continuous real-time display will be provided.
The indication may be on a dial, digital dis-play, or strip chart recorder. Recording of instrumentation readout information will be provided for at least one redundant channel.
The recording device need not be a as stated in paragraph 2. 1. 1. 1.
qualified'evice Direct and immediate trend or transient infor-mation that is essential for operator informa-tion or action, as .defined for type A variables, will be continuously available and displayed on a qualified recording device.
ik Otherwise, it will be displayed on an individual instrument or it will be continuously updated, stored in computer memory, and displayed. Intermittent displays such as data loggers and scanning recorders may also be used if no significant transient response information is likely to be lost by such devices.
2.1.6.2 Category 3 The instrument signal may be displayed on an individual instrument or it may be processed for display on demand. Signals from effluent radioactivity monitors, area monitors, and meteorology monitors shall be recorded. Direct and immediate trend or transient information that is essential for operator information will be available. Otherwise, it may be continuously updated, stored in computer memory, and displayed on demand. Intermittent displays such as data loggers and scanning recorders, may also be used if no .significant transient response information is likely to be lost by such devices.
2.1.7 Range
- 2. 1.7. 1 Category 1 If two or more instruments are needed to cover a parti,cular range, overlapping of instrument span will be provided. If the required range of monitoring instrumentation results in a loss of instrument sensitivity in the normal operating range, separate instruments will be used.
2.1.7.2 Category y 3 Same as category 1.
2.1.8 Equipment Identification 2.1.8.1 Category 1 Category 1 equipment identification on the control panels will be coordinated with the efforts to address item 5 of NURHG-0737, supplement 1, "Detailed Control Room Design Review."
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- 2. 1.8.2 Category 3 No specific provisions.
2.1.9 Interfaces 2.1.9.1 Category 1 Where applicable, the transmission of signals for use other than control room display will be through isolation devices that are designated as part of the monitoring instrumentation.
2.1.9.2 Category 3 No specific provisions.
2.1.10 Servicing, Testing, and Calibration
- 2. 1. 10. 1 Category 1 The inspection and testing programs for RG 1.97 instrumentation will be consistent with the applicable testing programs identified in the FSAR. Surveillance programs are maintained by the plant staff for servicing, .testing, and calibration of instrumentation and controls.
For those instruments where the required interval between testing is less than the normal time interval between unit shutdowns, a capability for testing during power operation is provided.
2.1.10.2 Category 3 Same as category 1.
2.1.11 Human Factors 2.1.11.1 Category 1 The instrumeritation will be designed to facilitate the recognition, location, replace-ment, 'repair, or ad)ustment of malfunctioning components or modules.
To the extent practical, the monitoring.
instrumentation design will minimize the development of conditions that would cause meters, annunciators, recorders, alarms, etc.,
to give anomalous indications potentially
0 confusing,to the operator. Human factors.
principles will be taken into consideration.
when determining the type and location of new displays.
To the extent practicable, the same instrumen-tation will be used for accident monitoring as is used for the normal operations of the plant to enable the operators to use, during accident situations, instruments with which they are most familiar.
- 2. 1. 11.2 Categor y 3 Same as category 1.
2.1.12 Direct Measurement 2.1.12.1 Category 1 To the extent practi'cable, monitor ing instrumentation input will be from sensors that directly measure the desired variables.
2.1.12.2 Category 3
- Same as category 1.
3.0 ,Variable Determination 3.1 Identification The emergency operating procedures and/or guidelines were used, a1ong with the guidance established in RG 1.97, as the basis for accident parameter selection. Tabl'e 1 conta.ins a summary, of the parameters, 'their classification, and range.
Attachment A lists variable types A through E. Each variable is listed individually with the following information included where applicable:
Identifier Variable Type Category Instrument Number Instrument Range Redundancy Power Supply Location of Display Schedule h Attachment B contains appropriate. Justification for deviations from RG 1.97 guidance.
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3.2 NUREG-0737 Instrumentation Where any parameter selected for RG 1.97 was also upgraded in response to NUREG-0737, the response to: the specific NUREG-0737 item will overrule the RG 1,.97 criteria are applicable if they differ. The to this situation:
following NUREG-0737 items II.B.3 Postaccident Sampling II.D.3, Valve Position Indication II.E.4.2 Containment Isolation Dependability II.F.1 Accident Monitoring
- 1. Noble Gas Monitor
- 2. Iodine/Particulate Sampling
- 3. Containment High-Range Monitor
- 4. Containment Pressure
- 5. Containment Water Level
- 6. Containment Hydrogen III.D.3.3 Inplant Radiation Monitoring 4.0 Technical Su ort Center and Emer enc 0 eratin Facilit Types A,, B, C, D, and E variables necessary for TSC and EOF functions wil1 be provided in the TSC and EOF, respectively by the use of the .
data systems identified in our letter from L. M. Mills to H. R. Denton dated April 15, 1983, in response to NUREG-0737, supplement 1. Tables 2 and 3 identify those parameters for the TSC and EOF, respectively.
5.0 Schedule TVA uses the concept of an integrated schedule for scheduling plant modi'fications. Each parameter listed in attachment A identifies a schedule for installing or upgrading the instrument to meet the stated configuration. If the parameter currently installed in the plant 'meets will state "Use As Is." If the the criteria outlined, the "Schedule" instrumentation is to be installed or upgraded, the "Schedule" will either be "In Accordance with Integrated Schedule" or "To Be
.Scheduled." If the design process for the modification is not complete, the aud'ification will not have been included on the integrated schedule; therefore, "To Be Scheduled" will appear in attachment A. When the design process has progressed enough to facilitate scheduling, it will then be included on the integrated schedule. The na)ority of the identified modifications already exist on the integrated schedule and attachment A identifies this by "In Accordance'with Integrated'chedule."
The schedule for providing .the identified parameters of tables 2 and' will also be implemented in accordance with the BFN integrated schedule.
0 0
TABLB'1'U!
fART O.,VARIA '
RG 1.97 1.'97 TVA Bo Al Variable Containnent Hydrogen Concertration TYY C-1'G Ct- ~Ran e VRT pe T~eCa-t A-1 T~TR R e 0- to 20-percent 0- to 100-percent See C11 Remarks A2 Drywell Pressure -5 to 3x dcsirn A-1 0 psia to 300 psig See B7, B9, C8, C10, D4, and Issue 5 A3 Dryuell Air Tenperature D-2 40oF to 440oF A-1 0 to <<OOoF See D7 81 Neutron Flux B-1 10 6 percent to B-3 10 6 percent to See Issue 1 100-percent 125 percent 82 Control Rod Position B-3 Full in or not B-3 Full in or not full in full in B3 RCS Soluble Boron Conct. B-3 0 to 1000 ppn B-3 Inplenent as 812 84 Coolant Level in Reactor B-1 Botton of'ore sup- B-1 1/3 core height to - See Issue 2 port plate to lesser, 228 inches above TAP of top of'essel or centerline of nain stean line.
B5 BUR Core Tenperature Hot required at this tine 86 RCS Pressure B-1 0 to 1500 psig B-1 0 to 1500 psig See C4 and Issue 3 Dryuell Pressure B-1 0 to design A-1 0 psia to 300 psig See A2, B9, Cg, C10, 04 and Issue 5 R
B8 Dryuell Sunp Level B-1 Top to Botton ~ B-3 0 to 150 gpn See C6 and Issue 4 B9 Primary Containnent Pressure B-1 -5 psig to design A-l 0 psia to 300 psig See A2, B7, C8, C10, D4, and Issue 5
II TABLE 1 (cont'd)
?0 1;97 RC 1.97 TYA Ro. Variable p C RanaRe ~Te 'Ca-t TVA R nv Remarks 910 PCIY Position B-1 Closed - Rot Closed B-1 Closed - Hot Closed See Issue 6 Cl Rad. Conc. or Level in Primary C-1 1/2 TS to 100 TS Implement as E12 See Issue 7 Coolant C2 Analysis of Primary Coolant 10 MCi/ml to Implement as E12 10 Ci/ml C3 BMR Care Temperature Rot requir d at this time C4 RCS Pressure C-1 0 to 1500 psig B-1 0 to 1500 psig See B6, C9, and Issue 3 C5 Primary Cont. Area Radiation C-3 1 R/hr to C-3 1 to 107 R/hr, See E1 105 R/hr C6 Drywell Drain Sump Level C-.1 Top to Bottom B-3 0 to 150 gpm See B8 and Issue 4 CT Suppression Pool 'Mater Level C-1 Bottom of ECCS C-1 0 to 240 inches (I) . See D5 suction line to 5 ft.
above normal water level CB Drywell Pressure C-1 0 to design A-1 0 psia to 300 psig . 'See A2, B7; B9, C10, D4, and Issue 5 C9 RCS Pressure C-1 - 0 to 1500 psig B 1 0 to 1500 psig See B6, C4, arid Issue 3 C10 Primary Containment Pressure C-1 -5 to 3x design A-1 0 psia to 300 psig See A2y B7p B9y C8 ~
D4, and Issue 5 C11 Cont. Hydrogen Concentration C-1 0 to 30 vol-percent A-1 0- to 20-'percent, See Al 0- to 100-percent
( .=. feet from bottom of orus to five feet a"ove normal water level.
~Ci TABLE '1 (cont'd)
RG 1.97 RG 1.97 TVA Nc Variable ~pe C-t. RanaRe ~TC -:lA F nA Remrks C12 Cont. Oxygen Concentration C-1 0 to 10 vol-percent C-3 0- to 25-percent See Issue 8 C13 Cont. Effluent Radioactivity C-3 10 6 DCi/cc to C-3 See Issue 9 10 2 MCi/cc C14 Effluent Radioactivity C-2 10 6 MCi/cc C-3 See Issue 9 See C13 10 " MCi/cc D1 Hain Feedwater Flow 0- to 110-percent D-3 0 to 16 x 106 lb/hr (0- to 119-percent design design)
D2 CST Level D-3 Top to Botton D>>3 0 to 32 feet (Rotten to Top)
Supp. Pool Spray Flow 0- to 110-percent Do not, inplenent See D8 and Issue 10 design Drywell Pressure -5 to 3x design A-1 0 psia to 300 psig See A2y B7y B9 Cg, psig and Issue 5 '10, D5 Supp. Pool Mater Level D-2 See C7 C-1 0 to 240 inches See C7 D6 Supp. Pool Mater Tenp. D=2 40oF to 230oF D-1 30oF to 230oF Drywall Atnosphere Tenp. 40oF to 440oF A-1 0 to 400oF See A3 Drywell Spray Flow D-2 0- to 110-percent Do not inplenent See D3 and Issue'0 design D9 HSIV Leakage Control Not applicable D10 HS/RV Position D-2 Closed - Not Closed D-3 Flow indication and 0 to 600oF D11 Isol. Cond. Shell-Side Mater Level Not applicable
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TABLE 1 (cont,'d)
RG 1.97 BG 1 ~ 97 TVA Ho. Va r f a'ale T~eCa-e ~Bar."e +pe-Cat ARAAVe TATA Reaarks D 1? Isol. Cond. Valve Position llot applicable D13 RCIC Flow D-2 0- to 1!n-percent D-3 0 to 700 gpa (0- to 117-percent design design)
D14 HPCI'low D-2 0- to 110-percent D-3 0 to 6000 gpa (0- to 120-percent design design)
D15 Core Spray Flow D-2 Or to 110-percent design D-3 0 to 10,000 gpa'0- to 160-percent design)
D16 LPCI Flow 0>> to 110-percent D-3 0 to 40,000 gpa (0- to 200-percent design design)
D17 SLY Flow D-2 0- to 110-percent Do not irpleaent, design See Issue 11 Dlg . SLCS Stoerage Tank Level D-2 . Top to Bottoa D-3 0 to 4850 gal. (Bottoa t'o Top)
D19 RHR Systea Flow D-2 0- to 110-percent D-3 0 to 40,000 gpa See D16 (0- to 200-design percent design)
D20 RHR Ht. Ex. Out. Tery. D>>2 40oP to 350oF D-3 0 to 600oF D21 Cooling Water Teap. to ESF OoF to 200oF D-3 0 to 600oF D22 Coolfng Water Flow to ESF D-2 0- to 110-percent D-3 0 to 7500 pga (0- to 160-percent desfgn design)
D23 High Rad. Lfqe Tank Level D-3 Top to Bottoa Do not iapleaent, see Issue 12 D24 Eaergency Vent. Daap. Positfon D-2 Open - Closed D-3 Open - Closed, See Table D24
0 TABLE 1 (cont'd)
RG 1.97 RG 1.97 TVA No Variable Rt RanaRe ~p-Cat A~
~~T~V~ nvTe Remarks D25 Status of'tandby Power D-2 D-3 Voltmeters, Acmeters
& VARs El Prim. Cont. Area Rad. E-1 1 R/hr to C-3 1 to 107 R/hr See C5 107 R/hr E2 RB or Sec. Cont. Area Rad E-2 10 1 R/hr to Do not i~lecent, 104 R/hr Sec Issue 13 Radiation Exposure Rate E-3 10 1 R/hr to E-3 10-1 to 103 mr/hr See Issue 14 104 R/hr E4 Noble Gases and Vent Flow E-3 See C13 and Issue 9 Particulates and Halogens E-3 10 3 1fCi/cc to E-3 See C13 and Issue 9
- 4. P 102 1jCi/cc 0- to 110-percent vent design flow E6 Airborne Radiohalogens and E-3 10 9 1fCi/cc to E-3 Laboratory analysis Particulates ~ 10-3 11Ci/cc Plant and Environs Radiation Portable Portable instrunentation Instrumentation EB Plant and Environs Radioactivity Isotopic analysis E-3 Portable instrumentation E9 Wind Direction E-3 0 to 360o 0 to 540o E10 Wind Speed E-3 0 to 50 mph E-3 0 to 45 cph, 0 to 100 mph Ell Atmospheric Stability E-3 -9oF to 18oF E-3 . -30oP to 30cF
0 TABLE 1 (conttd)
RG 1.97 RG 1.97 TVA Variable Ty n -t"- Ranee Tge-Cat tea RanVe Remarks E12 Primary Coolant and Sump o-3 Grab Sample See Issue 15 E13 Containment Air E-3 Grab Sample E-3 See Issue 16 KLArJLR 04/04/89 A6KA39.IH
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TABLE 2 TECHNICAL SUPPORT 'CENTER VARIABLES FROM REGULATORY GUIDE 1.'97 No. Variable A2 Drywell Pressure A3 Drywell Air Temperature 84 Coolant Level in Reactor B6 Reactor Pressure
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TABLE 3 EMERGENCY OPERATXONS FACXL'XTY VARXABLES FROM REGULATORY GUXDE 1-97 No. Variable A1 Containment Hydrogen Concentration A2 Drywell Pr essure A3 Drywe ll Temperature Coolant Level in Reactor B6 Reactor Pressure .
.High Range Pr imary Containment Radiation C7 Suppression Pool Water Level C12 Containment Oxygen Concentration.
C13 Conta.inment Effluent Radioactivity (Noble Gas)"
D6 Suppression Pool Water Temperature
'D13 RCXC Flow D14 HPCX Flow
'D15 Core Spray Flow D16 LPCX Flow Noble Gas and Vent Flow (C13)"
'E5 Particulates and 'Halogens'C13) +
E9 Wind Direction E10 Wind Speed E11 'Atmospheric Stability "When modifications are complete.
IDENTIFIER: (')
VARIABLE: Drywell and Torus Hydrogen Concentration TYPE: A, C CATEGORY:
INSTRUMENT NUMBER: H2I-76-37, H2R-76-37) H2I-76-39) H28-76-39 INSTRUMENT RANGE: 0 to 20%) 0 to 100% (2)
REDUNDANCY: 2 separate channels
'POWER SUPPLY: Class lE IOCATION OF DISPLAY: .Control Room REMARKS'S SCHEDULE: Use as is containment atmosphere approaches combustible limits.
~pnr oae: Maintain containment integrity, detection of potenti'al for breach, accomplishment of mitigation and long-term surveillance.
(~) See also Cll.
(2) Select range desired.
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IDENTIFIER: A2 VARIABLE: Drywell Pressure (~) (~)
A, B, C, D CATEGORY:
INSTRUMENT NUMBER: PI-64-67B, XR-64-50, PI-64-160A, XR-64-159 INSTRUMENT RANGE: 0 to 80 psia, 0 to 300 psig REDUNDANCY: 4 separate instrument loops, recorder point for XR-64-159 comes from PT-64-160B POWER SUPPLY.: Class lE
'LOCATION OF DISPLAY: Control Room SCHEDULE: 0 to 80 psia range - In accordance with integrated schedule.
0 to 300 psig range - Unit 1 use as is, units 2 and 3 in accordance with integrated schedule.
REMARKS:
sprays.
- ~Pur osa: Maintain containment integrity and maintain reactor coolant system integrity.
(~) NUREG-0737, item II.F.1.4 (wide range)'.
.( ) See also B7, B9, C8, C10,, D4 and Issue 5.
0 0
IDENTIFIER: A3 VARIABLE: Drywell Atmosphere Temperature (~)
TYPE: A, D CATEGORY:.
INSTRUMENT NUMBER: TI-64-52AB, XR-64-50 (~)
INSTRUMENT RANGE: 0 to 400oF REDUNDANCY: 2 separate channels POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: accordance with Integrated Schedule REMARKS'n
~Put ose: Provide indication of a potential for a breach in contai.'nment, support initiation of containment spray and verification of containment spray operation.
(~) See also D7.
,(~) Signal from TM-64-52CA is recorded on XR-64-50 along with drywell pressure.
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IDENTIFIER: Bl VARIABLE: Neutron Flux TYPE:
CATEGORY: 3 (1)
INSTRUMENT NUMBER SRMs, IRis, APRMs INSTRUMENT RANGE: 10 to 10 / power (SRM), .10 to 40/ power (IRM) 0 to 125$ power (APRM)(2)
REDUNDANCY: 4 SRMs, 8 IRMs, 6 APRMs POWER SUPPLY: Non-IE Battery Backed (SRM, IRM, Recorders) RPS (APRM)
LOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS:
P~ur oae: Reactivity control.
(~) See Issue 1 (2) SRMs and IRMs are inserted.
IDENTIFIER: B2 VARIABLE: Control Rod Position TYPE". 'B CATEGORY:
INSTRUMENT NUMBER: ZI-85-1 through ZI-85-185 INSTRUMENT RANGE: Full in to full out REDUNDANCY: N/A POWER SUPPLY: Non-1E Battery Backed LOCATION'F DISPLAY.: Control Room SCHEDULE: Use as is REMARKS:
~Pur ose: Verification of control rods full in dor reactivity control.
0 0
IDENTIFIER: B3 VARIABLE: RCS Soluble Boron Concentration (~) (Grab 'Sample)
'TYPE:
'CATEGORY:
INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A
'POWER SUPPLY: N/A LOCATION OF DISPLAY: N/A
'SCHEDULE: N/A REMARKS
~Pur ose: Verification of reactivity control after initiation of standby liquid control.
( ) See E12. This variable is encompassed by variable E12 which is satisfied by the Post-Accident Sampling Facility (PASF) in response to NUREG-0737', item II.B.3.
0 0
0
IDENTIFIER: B4 VARIABLE: Coolant Level in Reactor
'TYPE:
CATEGORY:
INSTRUMENT NUMBER: LI 3 52) LI 3 62Ae II 3 58Ag LI 3 588 g LI 3 55'100 INSTRUMENT 'RANGE: to +200 inches with zero at TAF (LI-3-62A)
-155 to +60 inches with zero at instrument zero (LI-3-58A,, LI-3-58B) 0 to 400 inches with zero at instrument zero (LI-3-55)( )( )
REDUNDANCY: 2 separate channels
'POWER SUPPLY: Class lE IOCATION OF DISPLAY: Control Room
'SCHEDULE: In accordance with integrated schedule.
REMARKS:
~Pur oee: Core cooling
(~) Total range is 1/3 core height to 228 inches above the Lop of active fuel (TAF)
-(2) See Issue 2A and 2B
0 II
IDENTIFIER: B5 VARIABLE: BWR Core Temperatures TYPE: Not required at this time ( )
CATEGORY: N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POVER SUPPLY: N/A LOCATION OF DISPLAY: N/A SCHEDULE: N/A REMARKS:
'(~) See also C3.
~
4l
IDENTIFIER: B6 VARIABLE: RCS Pressure (~)
TYPE: B, C CATEGORY:
'NSTRUMENT NUMBER: PI"3-74A and PI-3-74B (2)
INSTRUMENT RANGE: 0 to 1500 psig REDUNDANCY: 2 separate channels.
POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: In accordance with integrated schedule REMARKS
~Pur ose: Core cooling, maintain reactor coolant system integrity, detection of potential for or actual breach of reactor pressure boundary.
(~) See also C4 and C9.
(2) See Issue 3.
iO C
0
10 IDENTIFIER: B7 VARIABLE: Drywell Pressure (~) (2)
TYPE: See A, B, C, D CATEGORY:
.INSTRUMFNT NUMBER: PI-64-67B, XR-64-50, PI-64-160A, XR-64-159 INSTRUMENT RANGE: 0 to 80 psia, 0-300 psig REDUNDANCY: 4 separate instrument loops, recorder point for XR-64-159'omes from PT-64-160B POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: 0 to 80 psia range - In accordance with integrated schedule.
0 to 300 psig range - Unit use as is, units 1 2 and 3 in accordance with integrated schedule.
~pur oae: Detection of potential for or actual breach ot the reactor coolant system integrity, accomplishment of mitigation and verification.
(~) NUREG-0737, item II.F.1.4 (wide range).
(2) See-also A2, B9, C8, C10, D4 and Issue 5.
0 11 IDENTIFIER: B8 VARIABLE: Drywell Sump Level (~) (~).
TYPE: B, C CATEGORY: 3 (s)
INSTRUMENT NUMBER: FQ-77-6) FQ-77-16, FR-77-6 INSTRUMENT RANGE: 0 to 150 GPM REDUNDANCY: N/A POWER SUPPLY: Non-lE Battery Backed IOCATION OF DISPLAY: Control .Room SCHEDULE: Use as is REHARKS:
~Pur oae Detection of potential for or actual breach of the r<actor coolant system integrity, accomplishment of mitigation and verification.
(~) Drywell Equipment Drain Sump Flow Integrator, Drywell Floor Drain Sump Flow Integrator, Drywell Total Flow Recorder.
('2) . See also C6.
(~) See Issue 4.
12 IDENTIFIER: B9 VARIABLE: Primary Containment Pressure (~) (2)
TYPE: A) B, C, D CATEGORY:
INSTRUMENT NUMBER: PI-64-67B, XR-64-50, PI-64-160A, XR-64-159.
INSTRUMENT RANGE: 0 to 80 psia, 0 to 300 psig REDUNDANCY: 4 separate instrument loops, recorder point for XR-64-159 comes from PT-64-160B POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: 0 to 80 psia range - In accordance with integrated schedule.
0 to 300 psig range - Unit 1 use as is, units 2 and 3 in accordance with integrated schedule.
REMARKS:
~Pur oae: Detection of potential for ot actual breach of primary containment, accomplishment of mitigation and verification.
(~) NUREG-0737, item II.F.1.4.
( ) See also A2, B7, C8, .C10,, D4 and Issue 5.
0 il~
13 IDENTIFIER: B10 VARIABLE: Primary Containment Isolation Valve Position TYPE: B CATEGORY:
INSTRUMENT NUMBER: Status lights on control boards (~)
INSTRUMENT RANGE: Closed - Not closed REDUNDANCY: Redundant indication not required on each redundant isolation valve.
POWER SUPPLY:
LOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS:
~Pnr ose: Provide indicat;ion that containment isolation has been accomplished.
(~') See Issue 6 for list of valves and power supplies.
14 IDENTIFIER: C1 VARIABLE: Radiation Level in Circulating Primary Coolant TYPE: (')
CATEGORY: N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPLY:
IOCATION OF DISPLAY: N/A SCHEDULE: N/A REMARKS:
.(~) Implement as E12. See Issue 7'.
ijy n
4i 0
15 IDENTIFIER: C2 VARIABLE: Analysis of Primary Coolant (Gamma Spectrum)
TYPE: V)
CATEGORY:
INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPIY: N/A IOCATION OF DISPLAY:, N/A SCHEDULE: N/A
- REMARKS:
('~) This variable is encompassed in variable 'E12 which is, satisfied 'by the Post-Accident .Sampling Facility (PASF) in response -to NUREG-0737, item II.B.3'.
i41 IDENTIFIER: C3
'VARIABLE: BWR Core Temperature TYPE: Not required at this time. See 'B5, CATEGORY: N/A INSTRUMENT NUMBER: N/A
'INSTRUMENT RANGE: N/A
'REDUNDANCY: N/A POWER 'SUPPLY: N/A LOCATION OF DISPLAY: N/A SCHEDULE: N/A REMARKS
0 17 IDENTIFIER: C4 VARIABLE: RCS Pressure (~)
TYPE: B, C CATEGORY:
INSTRUMENT NUMBER: PI-3-74A and PI-3-748 INSTRUMENT RANGE: 0 to 1500 psig REDUNDANCY.: 2 separate channels POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: In accordance with integrated schedule REMARKS:
~Pur ose: Detection of potential for or actual breach oi the reactor coolant pressure boundary, accomplishment of mitigation and long term surveillance.
(~) See also B6, C9 and Issue 3.
18 IDENTIFIER:
VARIABLE: High Range Primary Containment Radiation (' ( )
TYPE: C, E CATEGORY:
INSTRUMENT NUMBER: RR-90-272CD, RR-90-273CD INSTRUMENT RANGE: 1 to 107 R/hr REDUNDANCY: N/A POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room REMARKS'5In accordance SCHEDULE: with integrated schedule
~Pur ose: Detection of a breach in the reactor coolant pressure 'boundary.
(~) NUREG-0737, item II.F.1.3.
(~2) See also El.
0 ill
19 IDENTIFIER: C6 VARIABLE: Drywell Drain Sump Level ( ) ( )
TYPE: B, C CATEGORY: 3 (s)
INSTRUMENT NUMBER: FQ-77-6, FQ-77-16, FR-77-6 INSTRUMENT RANGE: 0 to 150 GPM REDUNDANCY:
N/A'on-lE POWER SUPPLY: Battery Backed IOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS:
~pur ose: Detection of a breach in the reactor coolant pressure boundary, accomplishment of mitigation, verification and long-term surveillance.
( ) Drywell Equipment Drain Sump Flow Integrator, Drywell Floor Drain Sump Flow Integrator, Drywell Total Flow Recorder.
(2) See al'so BS.
(') See Issue 4.
ill 0~
20 IDENTIFIER: C7 VARIABLE: Suppression Pool Water Level (~) (~)
TYPE: C', D CATEGORY:
INSTRUMENT NUMBER: LI-64-159A, XR-64-159 INSTRUMENT RANGE: 0 to 240 inches (s)
REDUNDANCY: 2 separate channels POWFR SUPPLY: Class lE .
LOCATION OF DISPLAY: Control Room
'SCHEDULE: Unit 1 use as is, units 2 and 3 in accordance with integrated schedule.
REMARKS:
~Pur oae: Maintain containment integrity, detection of breach in reactor primary boundary.
(~) See also D5.
(~) NUREG-0737, item II.F.1.5 (3) Two feet from bottom of torus to five feet above normal .water'evel.
~ ~
2l IDENTIFIER: C8 VARIABLE: Drywell Pressure (~) (2)
TYPE: A, B, C, D CATEGORY: 1 INSTRUMENT NUMBER: PT-64-67B, XR-64-50, PI-64-160A, XR-64-159 INSTRUMENT RANGE: 0 to 80 psia, 0 to 300 psig REDUNDANCY: 4 separate instrument loops, recorder point for XR-64-159 comes from PT-64-160B POWER SUPPLY: Class lE
'LOCATION OF DISPLAY: Control Room 0 to 80 psia range - In accordance with integrated schedule.
SCHEDULE'EMARKS:
0 to 300 psig range - Unit 1 use as is, units 2 and 3 in accordance with integrated schedule.
~pur ose: Detection oy. a breach in the reactor coolant pressure boundary.
(~) NUREG-.0737, item II.F.1.4.
(2) See also A2, B7, B9, C10, D4, and Issue 5.
0 22 IDENTIFIER: C9 VARIABLE: RCS Pressure (~),
TYPE: B, C CATEGORY:
INSTRUMENT NUMBER: PI-3-74A and PI-3-74B INSTRUMENT RANGE: 0 to 1500 psig REDUNDANCY: 2 separate channels POWER SUPPIY: Class 1E LOCATION OF DISPLAY: Control Room SCHEDULE: In accordance with integrated schedule REMARKS:
~Pur oae: Detection of a potential for breach in the primary containment and accomplishment of mitigation.
(~) See also B6, C4 and Issue 3.
45 23 IDENTIFIER: C10 VARIABLE: Primary Containment Pressure (~) (~)
TYPE: A, B, C, D CATEGORY:
INSTRUMENT NUMBER: PI-64-67B, XR-64-50, PI-64-160A, XR-64-159 INSTRUMENT RANGE: 0 to 80 psia, 0 to 300 psig REDUNDANCY: 4 separate instrument loops, recorder point for XR-64-159 comes from PT-64-160B POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: 0 to 80 psia - In accordance with integrated schedule 0 to 300 psig Unit 1 use as is, units 2 and 3 in accordance with integrated schedule.
,REMARKS:
~pur oae: Detection of a potential for or actual breach of primary containment and accomplishment of mitigation.
( ) NUREG-0737, item II.F.1.4.
( ) See also A2, B7, B9, C8, D4 and Issue 5.
4l 24 IDENTIFIER: C11 (1)
VARIABLE: Containment Hydrogen Concent'ration TYPE: Aj C CATEGORY:
INSTRUMENT NUMBER: H2M-76-37, H2R-76-37, H2M-76-39'y H2R-76-39 INSTRUMENT RANGE: 0 to 20/,, 0 to 100/ (2)
REDUNDANCY: Two independent channels POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS p~ur oae: Detection of potential for breach in primary containment.
.(~) See also Al.
(2) Select range desired.
I, W
0
IDENTIFIER: C12 VARIABLE: Containment Oxygen Concentration T.YPE:
CATEGORY:
INSTRUMENT NUMBER: 02I-76-41A, 02I-76-43A, 02R-76-41, 02R-76-43 INSTRUMENT RANGE: 0 to 25%
REDUNDANCY: N/A POWER SUPPLY: Class 1E LOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS:
~Pur oae: Detection of a potential breach in the containment.
(~') See Issue 8.
Cl ik
26 IDENTIFIER: C13 VARIABLE: Containment Effluent Radioactivity Noble Gas (~) (2)
TYPE:
CATEGORY-:
INSTRUMENT NUMBER: Not yet assigned INSTRUMENT RANGE:
REDUNDANCY: N/A POWER SUPPLY: Not yet assigned LOCATION OF DISPLAY: Control Room SCHEDULE: In accordance with integrated schedule REMARKS:
P~nr oae: Detection of a breach of the containment:
(~) See Issue 9.
.(2) NUREG-0737 items II.F.l.l and II.F.1.2.
0 45
27 IDENTIFIER: C14 VARIABLE: Effluent Radioactivity - Noble Gas (~) (2)
TYPE:
CATEGORY:
INSTRUMENT NUMBER: Not yet assigned'/A INSTRUMENT RANGE:
REDUNDANCY:
POWER SUPPLY': Not yet assigned LOCATION OF DISPLAY: Control Room SCHEDULE: In accordance with integrated schedul.e REMARKS:
~Por oae: Detection of a breach of the containment,.
(~) See Cl'3 and Issue 9.
(2) NUREG-0737 items II.F.l.l and II.F'.1.2.
0 I!
0
28
'IDENTIFIER: Dl VARIABLE: Main Feedwater Flow
'TYPE:
'CATEGORY:
--INSTRUMENT NUMBER: FI-3-78A (Line A), FI-3-78B (Line B), FR-3-78 (Line ASB)
INSTRUMENT RANGE: 0 to 8 x 16 lb/hr, 0 to 8 x 10 lb/hr,,
0 to 16 x 106 lb/hr (~)
REDUNDANCY: N/A POWER SUPPLY: Non-lE Battery Backed
'IOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS:
~pnr ose: Verify operation of feedwater system and analysis of coolant flow.
( ) 0 to 119/ design flow
0 0
29 IDENTIFIER: D2
'VARIABLE: Condensate Storage Tank Level TYPE:
CATEGORY:
INSTRUMENT NUMBER: LI-2-161 (Unit 2), LI-2-165 (Unit 3), LI-2-169 (Unit 1) (')
INSTRUMENT RANGE: 0 to 32 feet (2)
REDUNDANCY: N/A POWER SUPPLY: Non-1E Battery Backed IOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS:
~Pur oae: Provide indication of available water for cooling.
(~) All indicators are located in unit l.
( ) Bottom to Top
II 41
30 IDENTIFIER: D3 VARIABLE: Suppression Pool Spray Flow (~)
TYPE: N/A CATEGORY: N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPLY: N/A LOCATION OF DISPLAY: N/A SCHEDULE: N/A REMARKS:
(~) Do not implement. See D8 and Issue 10.
0 0
31 IDENTIFIER:
VARIABLE: Drywell Pressure (~) (2)
TYPE: A, B, C, D CATEGORY:
INSTRUMENT NUMBER: PI-64-67B, XR-64-50, PI-64-160A, XR-64-159 INSTRUMENT RANGE: 0 to 80 psia, 0 to 300 psig REDUNDANCY: 4 separate instrument loops, recorder point for.
XR-64-159 comes from PT,-64-1608 POWER SUPPLY: Class 1E IOCATION OF DISPLAY: Control Room SCHEDULE: 0 to 80 psia range - In accordance with integrated schedule.
0 to 300 psig range - Unit 1 use as is, units, 2 and 3 in accordance with integrated schedule..
REMARKS.
~pur ose: To monitor operation of the primary containment, related systems.
( ')- NVREG-0737, item II.F.1.4.
(2) See also A2, 87, B9, C8, C10 and Issue 5.
0 4i
32 IDENTIFIER: D5 VARIABLE: Suppression Pool Water Level (~)
TYPE: C, D CATEGORY:
INSTRUMENT NUMBER: LI-64-159A, XR-64-159 INSTRUMENT RANGE: 0 to 240 inches (~)
REDUNDANCY: 2 separate channels POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: Unit 1 use as is, uni:ts 2 and 3 in accordance with integrated schedule.
REMARKS:
~Pur >ose: To monitor operation of the primary containment'elated systems.
(~) See also C7.
(~) Two feet from bottom of torus to five feet above normal water level.
0 K
IDENTIFIER: D6 VARIABLE: Suppression Pool Mater Temperature TYPE:
CATEGORY:
INSTRUMENT NUMBER: TI-64-161, 'TR-64-161 (Div. I)
TI-64-162, TR-64-162 (Div. II)
INSTRUMENT RANGE: 30 to 230 F REDUNDANCY: 2 divisions
'POWER SUPPLY: Class 1E IOCATION OF DISPLAY: Control Room
'SCHEDULE: Unit 1 use as is, units 2 and 3 in accordance .with integrated schedule.
REMARKS:
~Pnr ose: Maintain containment integrity, maintain reactor coolant system integrity.
34 IDENTIFIER: Dj VARIABLE: Drywell Atmosphere Temperature (~)
TYPE: A>. D CATEGORY:
INSTRUMENT NUMBER: TI-64-52AB, XR-60-50 (2)
INSTRUMENT RANGE: 0 to 400oF REDUNDANCY: 2 separate channel's POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: In accordance with integrated schedule REMARKS:
~pnr ose: To monitor operation of primary containment related systems.
a
(~) See also A3.
(2) Signal from TM-64-52CA is recorded on XR-64-50 along with drywell pressure.
~O II
-J
35 IDENTIFIER: D8 VARIABLE: Drywell Spray Flow (~)
TYPE: N/A CATEGORY: N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPLY: N/A LOCATION OF DISPLAY: N/A
'SCHEDULE: N/A REMARKS:
J
(~) Do not implement. See 93 and -Issue 10.
0 Cl 0
36 IDENTIFIER: D9 VARIABLE: Main Steam Line Isolation Valves Leakage Control System Pressure (~)
'TYPE: N/A CATEGORY: 'N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPI Y: N/A LOCATION OF DISPLAY: N/A.
SCHEDULE: N/A REMARKS:
(~) Browns Ferry does not have a MSIV Leakage Control'ystem - Not applicable.
0 37 IDENTIFIER:
'10 VARIABLE: Safety/Relief Valve Position (~)
TYPE:
CATEGORY: 3 (')
INSTRUMENT NUMBER: Tailpipe Thermocouples and Acoustic Monitors INSTRUMENT RANGE: 0 to 6000F, Flow Indication REDUNDANCY: Two diverse instrumentation systems POWER SUPPLY: Non-lE Battery Backed, Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS
~Per eee: Detection of an accident; boundary integrity indication, verification of vessel pressure control.
(~) This instrumentation was provided in response to NUREG-0737, item II.D.3 ~
The two instrumentation systems provide highly reliable indication of S/RV position which is used primarily for diagnostic purposes and thus Category 3 classification.
4l il 0
38
'IDENTIFIER: Dll VARIABLE: Isolation Condenser System Shell-Side ( )
TYPE: N/A CATEGORY: N/A INSTRUMENT NUMBER: N/A
, INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPLY: N/A LOCATION OF DISPLAY: N/A SCHEDULE: N/A REMARKS:
(~) Not appl'icabl'e to Browns Ferry.
0 0
39 IDENTIFIER:
VARIABLE: Isolation Condenser System Valve Position ('
TYPE: N/A CATEGORY: N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A
'REDUNDANCY.: N/A POWER SUPPLY: N/A REMARKS'12 LOCATION OF DISPLAY: N/A SCHEDULE: N/A
(~) Not applicable to Browns Ferry.
0 0
40 IDENTIFIER: D13 VARIABLE: RCIC Flow TYPE:
CATEGORY:
INSTRUMENT NUMBER: FIC-71-36A INSTRUMENT RANGE: 0 to 700 GPM (2)
REDUNDANCY: N/A
,POWER SUPPLY: Non-1E Battery Backed IOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS:
~pur oae: To monitor operation.
.( ) See Section 1.2.
( ) 0 to 117/ design flow
41 IDENTIFIER: D14 VARIABLE: HPCI Flow TYPE:
CATEGORY:
INSTRUMENT NJMBER: FIC-73-33 INSTRUMENT RANGE: 0 to 6000 GPM (~)
REDUNDANCY: N/A POWER 'SUPPLY: Class lE
',LOCATION OF DISPLAY: Control Room SCHEDULE: 'U'se as is
'REMARKS:
~pur oee: To monitor operation.
- ( ) See 'Section 1.2.
(~) 0 to 120$ design flow
i 0
42 IDENTIFIER: D15 VARIABLE: Core Spray System Flow TYPE:
'CATEGORY:
INSTRUMENT NUMBER: FI-75-21, FI-75-49 INSTRUMENT RANGE: 0 to 10,000 GPM (2)
'REDUNDANCY: N/A POWER SUPPLY: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: Use as is
,REMARKS:
~por oae: To monitor operation
(~) See Section 1.2.
'( ) 0 to 160/ design flow
0 0
0
IDENTIFIER: D16 VARIABLE: LPCI Flow TYPE:
'CATEGORY: 3 (')
INSTRUMENT NUMBER: FI-74-50,, FI-74-64, FR-74-64 INSTRUMENT RANGE: 0 to 40,000 GPM (2)
"REDUNDANCY: N/A POWER SUPPLY: Class lE, Non-1E Battery 'Backed (Recorder)
LOCATION OF DISPLAY: Control, Room SCHEDUIZ: Use as is REMARKS:
'~Pur oae: Monitor operation
(~.) See Section 1.2.
(2) 0 .to 200$ design flow
0 il 0
44 IDENTIFIER: D17 VARIABLE: SLCS Flow (~)
TYPE: N/A CATEGORY: N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A
'POWER SUPPLY: N/A
. ',L'OCATION OF DISPLAY: N/A
'SCHEDULE: N/A
,'REMARKS:
( ) Do not implement. See Issue 11.
0 45 IDENTIFIER: D18 VARIABLE:, SLCS Storage Tank Level TYPE:
,CATEGORY:,
INSTRUMENT NUMBER: LI-63-lA INSTRRKNT RANGE: 0 to 4,850 gallons (2)
REDUNDANCY: N/A POWER SUPPLY: Class lE IOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS:
~Pur oae: To monitor operation
( ) See Section 1.2.
- (~) Bottom to Top 4850 gallons is tank overflow.
II 0
46 IDENTIFIER: D19 VARIABLE: RHR System Flow TYPE: See D16 CATEGORY: N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPLY: N/A TOCATION OF DISPLAY: N/A SCHEDULE: N/A REMARKS:
~pur oae: To monitor operation.
~O 0
0
47 IDENTIFIER: D20 VARIABLE: RHR Heat Exchanger Outlet Temperature TYPE:
CATEGORY:
, INSTRUMENT NUMBER: TRS-74-80 (2)
INSTRUMENT RANGE: 0 to 600~F REDUNDANCY: N/A POWER SUPPLY: Non-lE Battery Backed LOCATION OF DISPLAY: Control Room
'SCHEDULE: ,Use as is REMARKS':
P~ur oae: To monitor operation
'(~') See Section 1.2.
'(~) Multipoint recorder displ'aying this variable.and D21.
II l
Cl 0
48 IDENTIFIER: D21 VARIABLE: Cooling Water Temperature to ESF Components (~)
TYPE:
CATEGORY: 3 (2)
INSTRUMENT NUMBER: TRS"74-80 (s) lNSTRUMENT RANGE: 0 to 6000 F REDUNDANCY: N/A POWER SUPPLY: Non-lE Battery Backed IOCATION OF DISPIAY: Control Room SCHEDULE: Use as is REMARKS:
~por oae: To Monitor Operation
( ) Interpreted as RHRSW to ME heat exchangers.
(2) See Section 1.2.
(s) Multipoint recorder displaying this variable and D20.
!I ik
49 IDENTIFIER:
VARIABLE: Cooling Water Flow to ESF System Components (~)
TYPE: D CATEGORY: 3 (~)
INSTRUMENT NUMBER: FI-23-36, FI-23-42, FI-23-48, FI-23-54 (s),
FI-67-3Ap FI"67-6A, FI"67-9Ap FI-67-12A (4)
I'NSTRUMENT RANGE: 0 to 7,500 GPM ( )
REDUNDANCY: N/A POWER SUPPLY: Class lE, Non-1E Battery Backed REMARKS'22 LOCATION OF DISPLAY: Control Room SCHEDULE: Use as is P~nr oae: To monitor operation
(~) Interpreted as RHRSW flow to RHR heat exchangers and EECW header flow.
(~) See Section 1.2.
(3) One per unit for a total of 12.
(4) Common for the three units but each has indication in each unit.
(5) 0 to 160$ design flow
0 0
0
50 IDENTIFIER: D23 VARIABLE: High Radioactivity Liquid Tank Level - Radwaste Systems TYPE:
CATEGORY: N/A INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPLY: N/A LOCATION OF DISPLAY: N/A SCHEDULE: N/A REMARKS:
(~) Do not implement. See Issue 12.
0 0
51 IDENTIFIER: D24 VARIABLE: Emergency Ventilation Damper Position TYPE:
CATEGORY:
INSTRUMENT NUMBER Status Lights ori Control Hoards (~)
INSTRUMENT RANGE: Open-Closed REDUNDANCY: N/A
'POWER SUPPLY:
IOCATION OF DISPLAY: ,Control Room SCHEDULE: Use as is REMARKS:
~pnr ose: To monitor operation of the ventilation system.
('~) See Section 1.2 ~
'(2) See Table D24.
0 52 Dam ers Havin Status Li hts in Control Room Table D24 Numbers Descri tion Power Su Control Room
.FCO"31-1508 Air supply to relay room and units 1 and 2 control room air handling units FCO-31-150D Fresh air supply to unit 3 FCO"31-150E Toilet room exhaust fan inlet isolation FCO-31-150F Unit 3 toilet room exhaust fan inlet (1) isolation FCO-31-151 Control room, (1)
FCO-31-152 Control room (1)
Refuelin Zone FCO-64-3A Refueling zone exhaust fan A (1)
FCO-64-38 Refueling zone supply fan A (1)
FCO-64-4A Refueling zone exhaust fan 8 (1)
FCO-64-48 Refueling zone supply fan 8 (1)
FCO-64-5 Refueling zone air supply outlet, (2) isolation FCO-64-6 Air supply inboard isolation (2)
FCO-64-7 Outside air isolation (unit 1 only) (2)
Pdco-64-8 Static pressure (2)
FCO-64-9 Exhaust duct outboard isolation (2)
FCO-64-10 Exhaust duct inboard isolation (2)
FCO-64-44 Refueling zone exhaust to SBGT (2)
(unit 1 only)
FCO-64-45 Refueling zone exhaust to SBGT (2)
(unit 1 only)
FCO-64-60A Stair hall exhaust fan supply (units 1 and 3)
FCO-64-608 Elevator machine room exhaust (units 1 and 3)
FCO-64-60C Refuel toilet room exhaust (unit 1) (1)
"'CO-64-60D Change room exhaust (unit 1) (1)
FCO-64-63 Refuel zone outside air (unit 1) (2)
Pdco-64-64 Static limiter (unit 1) (2)
FCO-64-65A Equipment access airlock inlet outboard (1)
(unit 1 only)
FCO-64-658 Equipment access airlock inlet inboard. (1)
(unit 1 only)
FCO-64-65C ~
Equipment access airlock exhaust (1) inboard (unit 1 only)
FCO-64-65D Equipment access airlock exhaust, (1) outboa d (unit 1 only)
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53 Dam ers Havin Status Li hts in Control Room (Continued)
Table D24 (Continued)
Numbers Descri tion Power Su l Reactor Buildin FCO-64-]1A Reactor building exhaust fan A '1)
FCO-64-]1B Reactor building supply fan A (1)
FCO-64-12A Reactor building exhaust fan B (1)
FCO-'64-12B Reactor building supply fan B (1)
FCO-64-13 Reactor zone air supply outboard (2) isolation FCO-64-]4A/B Reactor zone air supply inboard (2) isolation FCO-64-15 Reactor zone outside air isolation (2)
Pdco-64-16 Reactor zone static pressure (2)
FCO-64-40 Reactor zone exhaust to SBGT (2)
FCO-64-41 Reactor zone exhaust to SBGT (2)
'FCO-64-42 Reactor zone exhaust duct inboard (2) isolation FCO-64-43 Reactor zone exhaust duct outboard (2) isolation Standb Gas Treatment FCO-65-3 A train inlet (2)
FCO-65-4 A train decay heat removal (2)
FCO-65-16 SBGT Filter Bank A outlet (2)
FCO-65"17 SBGT Fan Inlet (2)
FCO-65-22 SBGT Filter Bank A and B Bypass (2)
FCO-65-25 SBGT Filter Bank B Inlet (2)
'CO-65-26 SBGT 'Filter Bank B Decay Heat (2)
FCO-65-38 SBGT Filter Bank B Outlet (2)
FCO-65-39 SBGT Fan B Inlet '(2)
FCO-65-51 C train inlet (2)
FCO-65-52 C train decay heat removal (2)
FCO-65-67 C train outlet (2)
(1) Station Power (2) Class lE
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54 IDENTIFIER: D25 VARIABLE: Status of Standby Power (~)
D TYPE'CATEGORY:
3 (2)
INSTRUMENT NUMBER: Diesel generator voltage, amperes and VARS (s)
INSTRUMENT RANGE:
REDUNDANCY: N/A POWER SUPPLY: Station Power LOCATION OF DISPLAY: Control Room SCHEDULE'. Use as is REMARKS:
~pur oae: To monitor operation
(~) Plant specific.
(2) See Section 1.2.
(s), No unique identifiers.
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55 IDENTIFIER: El VARIABLE: Primary Containment Area Radiation (~) (2)
TYPE: C, E CATEGORY:
.INSTRQfENT NUMBER: RR-90-272CD, RR-90-273CD INSTRUMENT RANGE: 1 to 107 R/l>r'/A iREDUNDANCY:
POWER SUPPLY.: Class lE LOCATION OF DISPLAY: Control Room SCHEDULE: Unit 1, use as is, units 2 S 3 in accordance with integrated schedule.
REl'fARKS:
~Pnr ose: Detection of significant releases; release assesss>ent, long term surveillance and emergency plan actuation.'1)
See a1so C5.
('~) NUREG-0737, item II.F,.1.3.
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56 IDENTIFIER: E2.
VARIABLE: Reactor Building or Secondary Containment Area Radiation TYPE CATEGORY.: 1N/A
'INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POVER SUPPLY': N/A LOCATION OF DISPLAY: N/A
'SCHEDULE: N/A REMARKS:
(~). Do not implement - See Issue 13.
0 57 IDENTIFIER: E3 VARIABLE: Radiation Exposure Rate (~)
TYPE: E CATEGORY:
INSTRUMENT NUMBER: RR-90-1 (~)
INSTRUMENT RANGE: 0.1'o 1,000 mr/hr REDUNDANCY: N/A POMER SUPPLY: 'Non-lE Battery Backed (Recorder)
Class lE (Monitors)
LOCATION OF DISPIAY:. Control Room
,'SCHEDULE: Use as, is REMARKS:
Purpose:
. Detection of significant releases, release assessment .and long term survei'llance.
(~) Inside buil'dings or areas where access is required to service equipment important to safety,. See Issue 14.
(2) Multipoint recorder. See Table E3 for list of points.
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58 TABLE E3 AREA RADIATION MONITORING POINTS Points Area 1 Fuel Storage Pool Area 2 Service Floor Area 3 New Fuel Storage Pool Area 4 M-G Set Area 5 Generator Operation Floor 6 Reactor Feed Pump Operation Floor 7 Turbine Operation Floor 8 Main Control Room 9 Cleanup Area ll Steam Jet Air Ejector Area 12 Feedwater Heater Area 13 North Cleanup System 14 South Cleanup System 15 Decontamination Area 16 Hotwell Pumps Area 17 Condenser Corridor 18 Condensate Area
~
19 Outside Steam Line Cavity 20 Control Rod Drive Hydraulic Control Unit West
.21'2 Control Rod Drive Hydraulic Control, Unit East TIP Room (10 to 10 mr/hr) 23 TIP Drive Room 24 HPCI 25 RHR West
- 26. Core Spray - RCIC 27 Core Spray Room 28 RHR East 29 Suppression Pool Area 30 Stack Room South West Booster Pump
0' 59 IDENTIFIER: E4 VARIABLE: Noble Gas and Vent Flow, Rate .(~)
TYPE: E.
CATEGORY:
INSTRUMENT .NUMBER: , N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPLY: N/A LOCATION OF DISPLAY: N/A SCHEDULE: N/A REMARKS:
~Pur ose: Detection of significant releases.
( ) See C13 and Issue 9.
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60 IDENTIFIER: E5 VARIABLE: Particulates and Halogens (~)
TYPE: E CATEGORY:
INSTRUMENT NUMBER: N/A INSTRUMENT,RANGE: N/A REDUNDANCY: N/A POWER SUPPLY: N/A LOCATION OF DISPLAY:. N/A SCHEDULE: N/A REMARKS:
~Pnr ose: Detection oE significant releases.
.(~) Particulates and halogens are measured by laboratory analyses of the particulate and carbon filters in the offgas stack exhaust
.radiation monitors. See .C13'nd Issue 9'.
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61 IDENTIFIER: E6 VARIABLE: Airborne Radiohalogens and Particulates (~)
TYPE: E CATEGORY:
INSTRUMENT NUMBER: N/A INSTRUMENT RANGE:
REDUNDANCY: N/A POWER SUPPLY: N/A LOCATION OF DISPLAY: N/A SCHEDULE: accordance with integrated schedule REMARKS'n
~Pnt ese: Release assessment and analysis.
(~) Laboratory analysis. This has been addressed in TVA response to NUREG-0737 item II.B.3, "Post-Accident Sampling Facility." See E12.
0 62 IDENTIFIER: E7 VARIABLE: Plant and Environs Radiation (~)
TYPE: E CATEGORY:
INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POWER SUPPLY.: N/A LOCATION OF DISPLAY: N/A
'SCHEDULE: Use as is REMARKS:
P~nt ese: Release assessment and analysis.
,( 1 ) Portable radiation monitors vill be used to measure radiati'on and airborne radioactivity concentrations in areas of concern..
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63 IDENTIFIER: E8 VARIABLE: Plant and Environs Radioactivity (~)
TYPE:. E CATEGORY:
INSTRUMENT NUMBER: N/A INSTRUMENT RANGE: N/A REDUNDANCY: N/A POSER SUPPLY:
N/A'OCATION OF DISPLAY: N/A SCHEDULE: Use as is P~nr ose: Release assessment and'nalysis.
,(~) Portable equipment.
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64 IDENTIFIER: E9 VARIABLE: Wind 'Direction TYPE: E CATEGORY:
'INSTRUMENT NUMBER: XR-90-102-2,. XR-90-103, XR-90-104 (1) iNSTRUMENT RANGE: 0 tp 540 REDUNDANCY: N/A POWER SUPPLY: Non-1E Battery Backed IOCATION OF DISPLAY: Control Room SCHEDULE: Use as is REMARKS P~ut nse: Release assessment.
(~) See E10 and El 1.
0 i
65 IDENTIFIER: Elo VARIABLE: Wind Speed TYPE: E CATEGORY:
INSTRUMENT NUMBER: XR-90-102-1,, XR-90-103, XR-90-104 (~)
lNSTRUMENT RANGE: 0 to 45 mph, 0 to 100 mph REDUNDANCY: N/A POWER SUPPLY: Non-lE Battery Backed LOCATION OF DISPLAY: Control room SCHEDULE Use as is REMARKS:
~Pur osn: Rel'ease assessment
(~) See E9 and Ell.,
0 66 IDENTIFIER: E1 1 VARIABLE: Atmospheric Stability TYPE:
CATEGORY:
INSTRUMENT NUMBER: TDR-90-103, TDR-90-104 (i)
INSTRUMENT RANGE: 30oF to 30 F REDUNDANCY: N/A POWER SUPPLY: Non-lE Battery Backed LOCATION OF DISPIAY: Control Room SCHEDULE: Use as is REMARKS
~Pnt ase: Release assessment.
(~) Meteorological parameter displays in the control room include wind direction (E9), wind speed (E10) and temperature differentials taken from the meteorological tower. The bT can be converted to an atmospheric stability class by comparison to a reference.
To initially determine offsite doses, the operators use tables in the REP Implementing Procedures. The REP-IP tables assume conservative meteorological conditions and give offsite doses at various distances (1 to 10 miles) using measured plant release rates. The Radiological Health Staff in Muscle Shoals will then routinely perform accident dose calculations using actual meteorological conditions.to provide more realistic offsite doses.
II 0
67 IDENTIFIER:
VARIABLE: Primary Coolant and Sump ( )
TYPE:
CATEGORY:
INSTRUMENT'UMBER: N/A INSTRUMENT RANGE:
REDUNDANCY: N/A
'POWER .SUPPLY:
REMARKS'12
'LOCATION OF DISPLAY:
,.'SCHEDULE: In accordance with Integrated Schedule
~Pns nss: Release assessment.
( ) See Issue 15. This variable is. satisfied by, the PASF in response:to NUREG-0737, 'item: II.'B.3.
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68 IDENTIFIER: E13 VARIABLE: Containment Air (~)
TYPE:
CATEGORY:
INSTRUMENT,NUMBER: See Al, Cll, C12, E12, and Issue 13 1NSTRUMENT RANGE: See Al, Cll, C12, E12, and Issue 13 REDUNDANCY: N/A POWER SUPPLY: See Al, Cll, C12, and E12 LOCATION OF DISPLAY: l'ontrol room for H2,and 02 SCHEDULE: Use as is for H2 and 02, see E12 for gamma spectrum.
REMARKS:
~Pur ose: R'elease assessment; verification and analysis.
(~) Grab sample -,See Issue 16.
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Issue 1 Variable Bl Neutron Flux Issue Definition Regulatory Guide (RG) 1.97 requires Category 1 instrumentation to monitor neutron flux for reactivity control. Category 1 instrumentation indicates that the variable being monitored is a key variable. In RG 1.97, a key variable is defined as "...that single variable (or minimum number of variables) that most directly indicates the accomplishment of a safety
'function ...." The following discussion supports the position that the neutron moni'toring instrumentation, as it currently exists, fully satisfies the intent of the guide for reactivity control.
Discussion The source range .monitors (SRMs), intermediate range monitors (IRMs), and average power range monitors (APRMs) provide neutron monitoring over the range of 10 -percent power to 125-percent power with the SRMs and IRMs inserted. The only event that would require the long-term monitoring of neutron flux is an anticipated transient without scram (ATWS) event. The neutron monitoring system is qualified for ATWS conditions.
'he drywell atmosphere after an ATWS event, remains similar to the condition during normal operation. The SRM and IRM drives and electronics are qualified for the normal drywell environment and thus for ATWS conditions.
That is, d'uring,'an ATWS, the 'SRMs and IRMs, are expected to .be inserted and be functional.
.Most portions of the neutron monitoring systems (SRMs, IRMs, and APRMs) are designed, procured, installed and tested to standards more stringent than Category 3. However, some portions, notably the SRM and IRM drive mechanisms and controls and the neutron monitoring system power sources., do not meet Category 1 requirements. Since there is a large number of neutron
.monitoring system channels (4 SRMs, 8 IRMs and 6 APRMs plus individual IPRM channels) that have a proven level of high reliability and the ATWS mitigation features have a lower importance to safety systems, a Category 3 cl'assification for neutron flux instrumentation is considered appropriate.
Conclusions Neutron monitoring instrumentation meets standards much more stringent than Category 3 but do not meet Category 1: requirements. But, due to .the proven reliability of the instrumentatipn and the large number of channels, the system as it is currently installed'> meets the intent of the guide.
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Issue 2A and 28 Variable B4 Coolant Level in Reactor Issue Definition A
.Regulatory Guide 1.97 requires redundant. instruments for Category 1 variables.
For reactor coolant 1'evel, redundant instruments would be available with a
,kange from 1/3 core height to 228 inches above the top of active fuel (TAF).
Contrary to that, redundancy is not provided for the full range.
Discussion A Three instrument ranges are being used to cover the total range: post-accident flooding (-100 to +200 inches with zero at TAF), emergency system flooding (-155 to +60 inches with zero, at instrument zero), and shutdown vessel flooding (0 to 400 inches with zero at instrument zero). Redundancy is provided for the postaccident flooding .and the emergency system flooding ranges. Only one instrument is provided for the shutdown vessel flooding range. This range takes its reference leg from the top of the reactor head.
In order to provide a second channel, an additional head penetration would be needed. No manual or automatic functions are initiated from the shutdown flooding range. Providing an additional channel would not result in any
.improvement in plant safety since no action is taken., A redundant channel, therefore, will not be implemented.
Conclusion A The redundancy provided for two of the three instrument ranges satisfies the intent of the guide and no redundant channel will be provided for the shut-down vessel flooding range.
'Issue Definition B Regulatory Guide 1.97 states that recording of instrumentation readout information be provided for at least one redundant, channel. Contrary to that, no recorder from a qualified instrument channel will be provided.
Discussion B Two independent qualified channels for indication are, provided in the control room for the postaccident flooding range"and the emergency system flooding range. They will not., however, have a recording device from a qualified channel in 'the control room. This information is not essential for the operator's direct and immediate trend or transient information.
Ifowever, a level recorder from a nonqualified instrument loop is provided for hot.h ranges. These ranges wil'lso be included in the database for the Safety Parameter Display System (SPDS).
Conclusion B Two independent control room indicators from qualified instrument loops for the postaccid'ent fl'ooding range and the emergency system flooding range is sufficient for operator's use during accident cond'tions. These ranges will also be input to the SPDS.
0 Issue 3 Variable B6 RCS Pressure Issue l)efinition Regulatory Guide 1.97 states that recording of instrumentation readout information will be provided for at least one redundant channel. Contrary
,to that, no recorder from a qualified instrument channel will be prove.ded .
for RSC pressure.
.Discussion
- .Reactor pressure is a Category 1 Type 8 variable. Two independent qualified channels for indication are provided in the control room. This parameter
.will not, however, have a recording device from a qualified channe'I. in the control room. This information is not essential for the operator's direct ind immediate trend'r transient information. It does, however, 'have a pressure recorder displayed in the control room that gets its signal from a nonqualifi~ d instrument 1'oop that the operators use during normal opera-t.ion. Reactor pressure will also be included in the database for,the Sajety Parameter Display System (SPDS).
Conclusions Two independent contro'l room indicators from a- qualified instrument loop for reactor pressure is sufficient for operator's use during acci'dent conditions. The reactor pressure will a'iso be input to the SPDS.
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Issue 4 Variables BS and C6 Equipment Drain Sump Flow Integrator (Identified Leakage)
Floor Drain Sump Flow Integrator (Unidentified Leakage)
Common Flow Recorder (Total Leakag<.)
Issue Dbfinition Regulatory Guide (RG) 1.9? requires Category 1 instrumentation to monitor.
drywell sump level and drywell drain sump level. These designations refer to the drywell equipment and floor dxain tank levels. Category 1 instrumen-tation indicates that the variable being monitored's a key variable. In RG 1.97, a key variable is defined as "...that single variable (or minimum number of variables) that most directly indicates the accomplishment of a safety function...." The following discussion supports the alternative position that the equipment drain sump flow integrator satisfies 'the intent of the drywell sump level of RG 1.97 and the floor drain sump flow integrator satisfies the intent ox the aryweil drain sump level of RG l'.97. The instrumentation should be classified as Category 3 instrumentation.
Discussion The B>Q Hark I drywell for Browns Ferry has two <irai>> sumus. <)ne dragon is the equipment drain sump, which collects identified leakage; the other is the floor dx'ain sump, which collects unidentified leakage. The drywell Leak detection system is designed to indicate, measure. and record leakage rates within the dryweil. ~lthougn the level of the sumps can oe a direct indication of breach of the reactor coolant system boundary, the indication is ambiguous because there is water in the sumps during normal operation. There is other instrumentation in the drywell leak detection system that would better indicate the amount of leakage thxougn the drywel.l equipment and floor drains, and there is,.other instrumentat<on required by RG 1.97 that also indicates leakage into the drywel'l.
'1'he drywe'il leak detection system has a preset level in the sump which starts the sump pumps and pumos the effluent to the radwaste system. The effluent flow rate is integrated with respec't to time to determine the number of gallons removed from the sump. If the pumps run too long or too frequent, an annunciator alarms aiertirsg the operator of the abnormal. leak rate. The instrumentation necessary in the control room to provide the opexator with the leakage amount is (1) the dryweil equipment drain sump flow <.ntegrator, <2) the drvwej.l floor drain sump flow integrator. and (3) a common flow recorder. !'bus, these three instruments indicate the amount oi
<irywell Leakage.
Regulatory Guide i.97 requires instrumentation to tunction during and after an accident. The drvweil sump systems are deliberatelv isolated at the primary containment penetration upon receipt of a Gxoup 2 isolation signal to establish. containment integrity. The sumo systems isolate on a reactor
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- low water level signal and a high drywell pressure signal'. This fact renders the sump flow recorders irrelevant. Therefore, by design, this instrumenta-tion serves no useful accident monitoring function and should be classified as Category 3.
However, as stated previously, there is other instrumentation required bg RG 1.97 that-also indicates leakage into the drywell. They are:
- 1. Drywell pressure - variable A2, Category 1
- 2. Drywell temperature - variable A3, Category 1
- 3. Primary containment area rad'iation variable C4, Category 3 Conclusions Based on the above discussions, the drywell equipment drain sump flow integrator, drywell floor drain sump flow. in'tegrator, and the common flow recorder satisfy the function of providing an indication of increasing dr~ell leakage before containment isolation. This instrumentation should
,be classified as Category 3..
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Issue 5 Variable B9 Primary Containment Pressure Issue Definition
,Regulatory Guide 1.97 requires Category 1 instrumentation to monitor primary containment pressure. Category 1 instrumentation indicates that the variable being monitored is a key variable, where a key variable is defined as "..; that single variable (or minimum number of variables) that most directly indicates the accomplishment of a safety function ...." The following discussion supports the position that the drywell pressure satisfies the intent of providing the primary containment pressure.
Discussion Primary containment pressure is monitored by the drywell pressure instrumentation which is classified as Category 1 Type A variable. The drywell and torus pressure may not be equal at all times; however, the drywell vacuum breakers 'have been designed to give assurance that torus pressure does not exceed drywell pressure by more than 2 psi. Also, the drywell pressure cannot exceed the torus pressure by greater than 1.5 psi due to the vent piping connections below the torus water level. Drywell/
torus differential pressure is bounded by 1.5 < AP < 2 psi, Therefore, drywell pressure can be used as an indication of torus pressure and drywell pressure provides the key variable for monitoring primary containment pressure.
Conclusion The key, variable for primary containment pressure is provided by drywell pressure which is a Categor'y 1, Type A. variable.
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Issue 6 Variables B10 Primary Containment Isolation Valve Position Issue Definition Regulatory Guide 1.97 requires Category 1 indication of the primary containment isolation valve position for the verification of accompli'shing containment isolation. Table 6.1 lists the isolation valves which will have their position indicated in the control room. Table 6.2 lists the isolation valves excluding check valves, which will not have their position indicated in the control room.
Discussion Table 6.2 lists the valves which will not have control room position indication. The notes for this table provide, the basis for this position.
Conclusions The present configuration as listed in tables 6.1 and 6.2 fully satisfies the intent of RG 1.97.
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TABLE 6.1 Primary Containment Isolation Valves Having Control Room Position Indication Valve Name Valve Number Power Su I Control Room Panel Notes Main Steam Line Isolation Valve 1-14 Class 1E 9-3 Main Steam Line Isolation Valve 1-15 Class lE 9-3 Main Steam Line isolation Valve 1-.26 Class 1E 9-3 Main Steam Line Isolation Valve 1-27 Class 1E 9-3 Main Steam Line Isolation Valve 1-37 Class 1E 9-3 Main Steam Line Isolation Valve 1-38 Class 1E 9-3, Main Steam Line Isolation Valve 1-51 Class 1E 9-3 Main Steam Line Isolation Valve 1-52 Class lE 9-3 Main Steam Line Drain Valves 1-55 Class lE 9-3 Main Steam Line Drain Valves 1-56 Class lE 9-3 Control Air 32-62 Class 1E 9-20 Control Air 32-63 Class 1E 9-20 Sampling and Water guality 43-13 Class 1E 9-15 Sampling and Water Quality 43-.14 Class 1E 9-5 Heating and Ventilation Air Flow 64-17 RPS 9-3 (1)
Heating and Ventilation Air Flow 64-1b RPS 9-3 (1)
Heating and Ventilation Air Flow 64-19 RPS 9-3 (1)
Heating and Ventilation Air Flow 64-20 Class 1E 9-3 He'ating and Ventilation Air Flow 64-21 Class 1E 9-3 Heating and Ventilation Air Flow 64-29 RPS 9-3 (1)
Heating and Ventilation'Air Flow 64-30 RPS 9-3 (1)
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TABLE 6.1 Primary Containment, Isolation Valves Having Control Room Position Indication (Continued)
Valve Name Valve Number Power Su 1 Control Room Panel Heating and Ventilation Air Flow 64-31 RPS 9-3 Heating and Ventilation Air Flov 64-32 RPS 9-3 Heating and Ventilation Air Flow 64-33 RPS 9-3 Heating and Ventilation Air Flow 64-34 RPS 9-3 Heating and Ventilation Air Flow 64-139 Class 1E 9-3 Heating and Ventilation Air Flov 64-140 Class 1E 9-3 Reactor Water Cleanup 69-1 Class 1E 9-4 Reactor Water Cleanup 69-2 Class 1E 9-4 Reactor Water Cleanup 69-12 Class 1E 9-4 Reactor Core Isolation Cooling ~ 71-2 Class 1E 9-3 Reactor Core Isolation Cooling 71-3 Class 1E 9-3 Reactor Core Isolation Cooling 71-6A Class 1E 9-3 Reactor Coie Isolation Cooling 71-6B Class 1E 9-3 Reactor Core Isolation Cooling 71-7A Class 1E 9-3 Reactor Core Isolation Cooling 71-7B Class IE 9-3 Reactor Core Isolation Cooling 71=14 Hon-1E Battery Backed 9-3 Reactor Core Isolation Cooling 71-32 Non-1E Battery Backed 9-3 Reactor Core Isolation Cooling 71-39 Class lE 9-3 Reactor Core Isolation Cooling 71-40 Class 1E 9-3 High Pressure Coolant In'jection 73-2 Class 1E 9-3 High Pressure Coolant Injection 73-3 Class 1E 9-3
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TABLE 6.1 Primary Containmcnt Isolation Valves Having Control Room Position Indication Valve Name Valve Number Pover Su 1v Control Room Panel Notes High Pressure Coolant Injection 73-6A Class 1E 9-3 High Pressure Coolant Injection 73-68 Class 1E 9-3 High Pressure Coolant Injection 73-17A Class 1E 9-3 High Pressure Coolant Injection 73-17B Class 1E 9-3 High Pressure Coolant Injection 73-23 Class 1E 9-3 High Pressure Coolant Injection 73-.44 Class 1E 9-3 High Pressure Coolant Injection 73-45 Class 1E 9-3 (2)
High Pressure Coolant Injection 73-81 Class 1E 9-3, Residual Heat Removal 74'-47 Class 1E 9-3 Residual Heat Removal 74-48 Class 1E 9-3 Residual Heat Removal 74-53 Class IE 9-3 Residual Heat Removal 74-54 Class lE 9-3 Residual Heat Removal 74-57 Class IE 9-3 Residual Heat Removal 74-58 Class 1E 9-3 Residual Heat Removal 74-60 Class 1E 9-3 Residual Heat Removal 74-61 Class, 1E 9-3 Residual Heat Removal 74-67 Class 1E 9-3 Residual Heat Removal 74-68 Class lE 9-3 ~ (2)
Residual Heat Removal 74-71 Class 1E 9-3 Residual Heat Removal 74-72 Class 1E 9-3
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TABLE 6.1 Primary Containment Isolation Valves Having Control Room Position Indication (Continued)
Valve Name Valve Number Pover Su 1 Control Room Panel Notes Residual Heat Removal 74-74 Class 1E 9-3 Residual Heat Removal 74-.75 Class 1E 9.-3 Residual Heat Removal 74-77 Class 1E 9-3 Residual Heat Removal 74-78 Class 1E 9-3 Residual Heat Removal 74-102 Class 1E 9-3 Residual Heat Removal 74-103 Class 1E 9-3 Residual Heat Re~oval 74-119 Class 1E 9-3 Residual Heat Removal 74-120 Class 1E 9-3 Core Spray 75-25 Class 1E 9-3 Core Spray 75-26 Class 1E 9-3 (2)
Core Spray 75-53 Class 1E 9-3 Core Spray 75-54 Class IE 9-3 (2)
Core Spray 75-57 Class 1E 9-3 Core Spiay 75-58 Class 1E 9-3 Containment Inerting 76-17 RPS 9-3 (1)
Containment Inerting 76-18 RPS 9-3 (1)
Containient Inerting 76-19 RPS 9-3 (1)
Containment Inerting 76-'24 RPS 9-3 (1)
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TABLE 6.1 Primary Containient Isolation Valves Having Control Room Position Indication (Continued)
Valve Name Valve Number Poser Su lv Control Room Panel Notes Drp:ell Equipment Drain Valves 77-2A RPS 9-4 (1)
Dry'ell Equipment Drain Valves 77-2B RPS 9-4 (1)
Dry:ell Floor Drain Valves77-15A RPS 9-4 (1)
Drp ell Floor Drain Valves77-15B RPS 9-4 (1)
Containment Atmospheric Dilution 84-SA Class 1E 9-54 Containment, Atmospheric Dilution 84-8B Class 1E 9-54 Containment Atmospheric Dilution 84-8C Class 1E 9-54 Containr:ent Atmospheric Dilution 84-SD Class 1E 9-54 Containaent Atmospheric Dilution '4-19 Class 1E 9-55 Containment Atmospheric Dilution 84-20 RPS, 9-55 Containment Radiation Honitoring 90-254A Class 1E 9-2 Containment Radiation Honitoring 90-254B Class 1E 9-2 Containment Radiation Honitoring 90-255 Class IE 9-2 Containment Radiation Honitoring 90-257A Class 1E 9-2 Containment Radiation Honitoring 90-257B Class 1E 9-2 Notes: '1) Valve fails close on loss of poMer.
(2) This is a check valve which is not required to have control room position indication.
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Table 6.2 Primary Containment Isolation Valves Not Having Control Room Position Indication (Excluding Check Valves)
Name Valve Number Note Demineralized Water 2-1383 1 Compressed Air 33-1070 1' Sampling and Water Quality 43-28A
'Sampling and Water Quality 43-28B 2 Sampling and Water Quality 43-29A 2 Sampling anil Water Quality 43-29B 2 High Pressure Coolant Injection 73-24 3 Residual Heat Removal 74-722 1 Containment Inerting System 76-49 4 Containment Inerting System 76-50 4 Containment Inerting System 76-51 4 Containment Inerting System 76-52 4 Containment Inerting System 76-53 4 Containment Inerting System 76-54 4 Containment Inerting System 76-55 4 Containment Inerting System 76-56 4 Containment Inerting System 76-57 4 Containment Inerting System 76-58 4 Containment Inerting System 76-59 4 Containment Inerting System 76-60 4 Containment Inerting System 76-61 4 Containment Inerting System 76-62 Containment Inerting System 76-63 4 Containment Inerting System ,76-64 4 Containment Inerting System 76-65 4 Containment Inerting System 76-66 4 Containment Inerting .System 76-67'6-68 4 Containment Inerting System 4
- 1. This valve is locked closed.
- 2. Local control pushbutton energizes two valves (A and B) simultaneously. Valves are normally closed.
- 3. Valves locked open. Isolation provided, by a check valve.
- 4. Isolation signal indicated on control room panel 9-54 for system A and 9-55 for system B. Keylock provides an isolation override. One handswitch per system controls all valves in that system from their respective control room panel. These valves are part of the H2/02 monitoring system. which is needed for post-accident monitoring.
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Issue 7 Variable Cl Radioactivity Concentration or Radiation Level in Circulating Primary Coolant Issue Definition Regulatory Guide (RG) 1.97 specifies that the status of the fuel cladding be monitored during and after an accident. The specified variable to accomplish this monitoring is variable Cl--radioactivity concentration or radiation level in circulating primary coolant. The range is given as "1/2 Tech Spec Limit to 100 times Tech Spec Limit, R/hr." In Table 2 of 'RG 1.97, instrumentation for measuring variable Cl is designated as Category 1. The purpose for monitoring this variable is given as "detection of breach",
referring, in thi's case, to breach of fuel cladding.
Discussion As stated above, the, purpose of monitoring this variable is given as detecting a breach in the fuel cladding. The critical actions that must be taken to prevent and mitigate a gross breach of fuel cladding are (1) shut down the reactor and (2) maintain water level. Monitoring variable Cl, as, directed in RG 1.97, will have no influence on either of these actions, and no operator action based on, this variable has been identified. The variable, therefore, should be Category 3.
Regulatory Guide 1.97 specifies measurement of the radioactivity of the circulating primary coolant as the key variable in monitoring fuel cladding status during isolation of the NSSS. The words "circulating primary coolant" are interpreted to mean coolant, or a representative sample of such coolant, that flows past the core. A basic criterion for a valid measurement of the specified variable is that the coolant being monitored is coolant that is in active contact with the fuel, that is, flowing past the failed fuel.
Monitoring the active coolant (or a sample thereof) is the dominant consider-ation. The post-accident sampling facility (PASF), in response to NUREG-0737, provides a representative sample which can be monitored.
The subject of concern in the RG 1.97 requirement is assumed to be an isolated NSSS that is shut down. This assumption is justified as current monitors in the condenser off-gas and main steam lines provide reliable and accurate information on the status of fuel cladding when the plant is not isolated. Further, the post-accident sampling facility (PASF) will provide an accurate status of coolant radioactivity, and hence cladding status, once the PASF is activiated. In the interim between NSSS isolation and operation of the PASF, monitoring of the primary containment radiation and containment hydrogen .will provide information on the status of the fuel cladding.
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Conclusions The"designation of instrumentation for measuring variable Cl should be Category 3, because no planned. operator actions are identified and no operator actions are anticipated:based on this variable serving as the key variable. This variable will be monitored as Type E Category 3. See Variable E12.
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Issue 8 Variables C12 Drywell and Torus Oxygen Concentration
'ssue Definition
<<l Regulatory Guide 1.97 has designated the containment and drywell oxygen concentration as a Category 1 variable for the detection of potential for a
,breach in the containment. The following discussion supports the position
'that the drywell and torus oxygen concentration should be classified as Category 3.
Discussion The function of detection of a potential for a breach in the containment is also monitored by the following variables;
'(1) Drywell pressure - Type A, Category 1 (2) Drywell and Torus Hydrogen Concentration - Type A, Category .1 (3) Reactor pressure - Type B, Category 1 The torus and drywell oxygen concentration is, not used to initiate a safety function or to key the operator to perform a manual acti. on. Browns Ferry's primary containment is operated with an oxygen deficient (i.e., inerted) atmosphere is one part of those measures for combustible gas control. The Containment .Atmospheric Dilution (CAD) system is used following a postulated loss-of-coolant accident (LOCA) to dilute the containment atmosphere with nitrogen to maintain the hydrogen and oxygen concentrations below combustible levels. Hydrogen concentration is used at Browns Ferry to alert the operators to manually, initiate the CAD .System (H~ concentration is a Type A variable). The 0~ concentration is used only as a surveillance instrument. NRC approved this configuration for units 1, 2, and 3 in technical specification amendments 38, 36, and 12 respectively.
Conclusion Oxygen concentration is not a key variable and should be classified as Category 3.
0 Issue 9 Variables C13 and C14 Containment Effluent Radioactivity - Nobl'e Gas (C13)
Effluent Radioactivity - Noble Gas (C14)
Issue DeCinition Regulatory Guide 1.97 Iists item C13 as containment effluent.,radioactivity-noble gases (from identified release points including Standby Gas Treatment System Vent) and item C14 as effluent radioactivity - noble gas .(from
,buildings or areas where penetrations and'atches are located). These two variabl'es have been addressed, by NUREG-0737 item II.F.l..l.
'Discussion TVA has committed to installing a system to monitor the Browns Ferry stack for high-range noble gas with particulate and iodine collection on appropriate collection media in response to NUREG-0737, item II.F.l.l and II.'F ..1.2.
The Browns l'erry plant is designed to have one designated'elease point; namely, the stack. The secondary containment features of the plant and/or realign to cleanup systems, which exhaust to the designated will'solate
, release point. Therefore,'there is a very low probability of a maj or release of activity within other plant zones such as the turbine building.
lf an accidental release does occur in other areas, a high-radiation alarm is received and the effluent vent dampers '(variable D24) and fans can be quickly isolated. Since release paths such as the turbine building vents do not have cleanup systems, the isolation and/or shutdown of these ventilation system exhausts are stopped, it is not possible to determine quantitative releases.
Conclusi'ons The variables C13 and .C14 are encompassed by. the scope of the above described'ystem and: wi'll,be installed as Category, 3 variables.
Issue l0 Variables D3 and D8 Suppression Pool Spray Flow Drywell Spray Flow
'Issue Definition Regulatory Guide 1.97 specifies flow measurements of suppression pool spray (variable D3) and drywell spray (variable -D8) for monitoring the operation of the primary containment-related systems. Instrumentation for measuring these variables is designated Category 2, with a range of 0 to 110'ercent of design flow. These flows relate to spray flow for controlling pressure and temperature of the .drywell and suppression pool. The following discussion supports the position th'at these variabl'es are not needed'.
Discussion
'The drywel'l sprays can be used to control the pressure and temperature of the drywell. Likewise, the suppression pool sprays can, be used to control the pressure and temperature in the torus. The flow to the sprays is monitored by a flow element which is common to both the drywell spray flow and the suppression pool spray flow. This flow element is monitored as variable DJ6, IPCI flow. The operator can determine that the indicated f'low is the flow that is being diverted'o the sprays by observing the
,position (in the main control room) of the valves in the 'RHR line. The effectiveness of these flows can be verified by pressure and temperature changes of. the drywell and the torus. The drywell pressure and drywell temperature instrumentation have been classified as Category 1.
Conclusion The current plant design,, ln conjunction with operating practic<<, provides lor op~ rotor information that is sutficient for determining th<< existence of,:;pray flows Lo t.'he dry'well and,suppression,poo.t.'ithout the use of a dedicated f;low-measuring instrument. Dedicated instruments, therefore, are
,not needed.
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Issue ll'ariable D17 Standby Liquid Cont;rol, System (SLCS) Flow issue Defirrition Regulatory Guide (RG) 1.97 requires a Category 2, Type D'nstrument for indicating standby liquid control system (SLCS) flow in the control room.
The purpose of this. instrument is to monitor the operation of the standby liquid control system. The following discussion justifies TVA's position that SLCS flow is not needed in .the control room.
,Discussion
'The SLCS flow, as discussed in RG 1.97, is to monitor the operation of the (SLCS). The SLCS tank level is monitored in the control room along with pump operation. When the squib valves are opened and SLCS pumps started,
.the totaL contents of. the, tank are pumped 'to the reactor. Flow through the
'l'inc to the reactor is indicated by an annunciator and a white li'ght. The actual amount of flow to the reactor is not relevant since tire total volume o'f t,he t..ank is to be pumped. SLCS operation is adequately morri.t.ored by (1) t;ank 'leve1 decreasing,, (2) pump operabiU;ty indication, and (3). neutron flux resporise. The inrlication of the amount of flow is not necessary to ensure syst: em operation.
Conclusion The SLCS flow is not a necessary, parameter for monitoring system operation and will not be implemented at Browns Ferry.
Issue 12 Variable D23 High Radioactivity Liquid Tank Level - Radwaste System Issue Definition Regulatory Guide 1.97 states that high radioactivity liquid tank 'level (i.e., liquid level of the floor drain collector tank of the radwaste system) is a Type D Category 3 and is used to monitor the operation of the system. The following discussion supports the position that the variable is not .needed for post-accident monitoring.
Discussion The radioactive waste systems are designed to dispose of the radioactive process wastes generated during plant operation. The system is designed to prevent the inadvertent release of significant quantities of radioactive material from the restricted area of the plant so that resulting exposures are within the guideline values of 10CFR20. The radwaste facility is located in the Radwaste Building. The Radwaste Building has been designed to withstand a design basis earthquake (DBE). Should the floor drain collector tank fail or overfill before isolation, the spilled liquid would be retained in the building. Because the leaks or spills from the radwaste system are retained within the radwaste building and have little or no effect on the site boundary dose rate and the radwaste system is not required after a DBA, the level of the floor drain collector tank is not required to monitor the operation of the system.
Conclusions The level of the floor drain collector tank is not required for post-accident monitoring. It does not add to the safe operation of the system nor is it necessary to maintain offsite release rates below the guidelines. It, therefore, will not be implemented.
0 Issue 13 Variable E2 Reactor 'Building or Secondary Containment Area Radiation Issue Definition Regulatory Guide 1.97 specifies .that "Reactor building or secondary containment area radiation" should be monitored over the range of 10 to 10~ R/h as a Category 2 variable. Th'e reason for monitoring this parameter is for detection of a significant release from the primary containment.
Discussion The use of local radiation monitors to detect a breach or leakage through primary coritainment penetrations is inappropriate. In general, radiation in the secondary containment will be largely a function of radioactivity in primary containment and in the fluids flowing in ECCS piping, which will cause direct radiation. shine on the area monitors. Also, because of the amount of piping and,the number of electrical penetrations and hatches and their widely scattered locations, local area radiation monitors could give ambiguous indications. The proper way to detect a breach of containment is
,by using the stack noble gas monitors (C13 and C14).
Conclusions Variables C13 and C14 satisfy the intent of this parameter; therefore, the reactor building area radiation monitors will not be implemented.
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Issue 14 Variable E3 Radiation Exposure .Rate Issue Definition Regulatory Guide 1.97 specifies in Table 2, variable E3, that radiation
.exposure rate (i'nside buildings or areas where access is required to servi'ce equipment important to safety) be monitored over the range of 10 ~
to 10 R/hr for detection of significant releases, for release assessment, and for long-term surveillance.
Discussion In general, .access is not required to any area of the secondary containment in order to service equipment important to safety in a post-accident situation. If and when accessibility is reestablished in the long term, will be done by a combination of portable radiation survey instruments and it
-post-accident sampling of the secondary containment atmosphere. The existing lower range (..1 to 10 mr/hr) area. radiation monitors would be used only in those instances in which radiation levels were very mild.
Conclusions Since access to a harsh environment area to servi'ce safety-related equipment. during an accident is not required, this parameter should be modified to all'ow credit for existing area radiation monitored with lower range.
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Issue 15 Variable E12 Primary Coolant and Sump Issue Definition Regulatory Guide 1.97 requires installation of the capability of obtaining grab samples of the containment sumps,. ECCS pump-room sumps, and other similar auxiliary building sumps for the purpose of release assessment, verification, and analysis.
Discussion Primary coolant and sump monitoring were addressed'n TVA's response to NUREG.-0737,, item II.B.3, post-accident sampling facility (PASF). Gross activity, gamma spectrum, boron content, chloride content, dissolved hydrogen, dissolved oxygen, and pH determination are made availabl'e, Grab samples are .taken, from the reactor coolant and containment atmosphere. It is TVA's position that NUREG-0737, item II.B.3, satisfies the intent of this item.
Conclusions NUREG-0737, item II.B.3, satisfies the intent of variable E12. It, therefore, will'ot be implemented.
0 Issue 16 Variable E13 Containment Air - Grab Sample L
Issue Definition Regulatory Guide 1.97 specifies the capability to obtain containment air grab samples for hydrogen content,, oxygen -content, and gamma spectrum analysis..
Discussion The hydrogen and oxygen concentration of the containment air is monitored by variables,A1 and Cll for hydrogen and C12 for oxygen. The gamma spectrum analysis is -provided by the post-accident sampling facility in response to NUREG-0737, i:tern 'II.B.3.
Conclusions The above discussion satisfies the intent of variable E13.
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