ML20151U461
| ML20151U461 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/31/1988 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20151U439 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8808190109 | |
| Download: ML20151U461 (93) | |
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l ENCLOSURE i
REVISED RESPONSE TO NUREG-0737 SUPPLEMENT 1, SECTION 6.0 i
REVIEW OF REGULATORY GUIDE 1.97 -
APPIICATION TO EMERGENCY RESPONSE FACILITIES, CALVERT CLIFFS NUCLEAR POWER PLANT BALTIMORE GAS AND ELECTRIC COMPANY l 4
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i AUGUST 'O8 pi Q$8$N N P
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1.0 INTRODUCTION
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SUMMARY
As stated in Section 1.1 of the Updated Final Safety Analysis Report (FSAR) the Calvert Cliffs Nuclear Power Plant was designed in accordance with the 70 design criteria published by the Atomic Energy Commission on July 11, 1967.
Inasmuch as these original criteria were revised and regrouped into the 64 General Design Criteria (GDC) that were subsequently issued a.: Appendix A to 10 CFR 50, the Calvert Cliffs design continues to satisfy these criteria.
Specifically, instrumentation currently provided at Calvert Cliffs to assess plant and environs conditions during and following a design basis accident (DBA) satisfies GDC 13, "Instrumentation and Control," GDC 19, "Control Room," and GDC 64, "Monitoring Radioactivity Releases," as described in Section 7 of the Updated FSAR.
Supplement I to NUREG-0737 requires all licensees to review the post-cccident I monitoring (PAM) instrumentation available at their facility and to corppare this instrumentation witn the recommendations of Regulatory Guide 1.97 . In December, 1984, we presented the results of our review of the provisions for post-accident monitoring at the Calvert Cliffs Nuclear Power Plant. Over thrw years have elapsed since this review and we now find it necessary to revise the previously submitted report.
Attachment A summarized the significant changes that we have made.
Attachment B is the report in its entirety with revision bars in the right margin to denote changes to the December 1984 report.
Attachment B provides the results of our review of each of the post-accident monitoring variables identified in Regulatory Guide 1.97 (R.G. 1.97). Where instrumentation available at Calvert Cliffs deviates from the recommendations of R.G. 1.97, Attachment B provides either a justification for the deviation or a commitment to assess the need for physical plant upgrades. The results of our review are summarized in Table 1.
Those modifications which BG&E has determined to be warranted will be accomplished under our facility change request (FCR) process in a manner consistent with existing procedures. These procedures reflect the need for established priorities consistent with the safety significance of the modification and for performing additional design evaluation to better define the required scope of effort. A schedule for implementing the proposed upgrades is shown on Table 2.
I Regulatory Guide 1.97, Revision 3 Instrumentation for Light-Water Reactor Plants to Assess Plant and Environs Conditions During and Following an Accident.
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- 2. SELECTION OF VARIABLE TYPE AND CATEGORY 2.1 General The recommendations of R.G.1.97, Revision 3, were used in our preliminary I review of PAM instrumentation to identify the r.tquired monitoring function (variable type) and classification (variable category). These initial designations were then evaluated against the specific function and safety significance of the PAM instrumentation at Calvert Cliffs as defined in the Updated FSAR and the plant emergency operating procedures. This evaluation was performed in parallel with our selection of variables to be displayed on the safety parameter display system (SPDS).
As a result of the above evaluation, the type and category of certain PAM variables viere revised as summarized below. The rationale for these changes is provided in Attachment B. l Change No. of VariahJn Category I revised to Category 3 1 Category 2 revised to Category 3 9 i New variables added to Category 3 2 2.2 Tvoe A Variables Type A variables were initially selected from a review of the event-oriented Calvert Cliffs Emergency Operating Procedures (EOPs) to identify those l variables which would provide primary information to the plant operators to support pre-determined manually controlled actions for which no automatic control is provided and which are required for safety systems to accomplished their safety function. The list of Type A variables generated during this review was then compared with the operator actions specified in the new function-oriented EOPs to verify that the list was complete and accurate, i j The Type A variables are shown below. l 1
l Pressurizer Level (A-1) l Pressurizer Pressure (A-2)
Steam Generator Pressure (A-3)
Steam Generator Level (A-4)
Resctor Coolant System Hot Leg Temperature (A-5)
Reactor Coolant System Cold Les Temperature (A-6) ,
Subcooled Margin (A-7) !
Condensate Tank No.12 Level (A-8) i Containment H2Concentration (A-9) l Containment Pressure (A-10) j All Type A variables were classified as Category 1 in accordance with the guidelines of h.G.1.97 and were evaluated accordingly. q 1
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- 3. DESIGN AND QUALIFICATION CRITERIA 3.1 General The twelve design and qualification criteria presented in R.G.1.97 were used as the basis for comparison. However, it should be recognized that certain of the current recommended design standards and criteria are not appropriate for Calvert Cliffs. Nevertheless, BG&E believes that the intent of the recommended design and qualification criteria are met.
3.2 Envioment Oualification 3.2.1 Category I and 2 BG&E's equipment qualification program includes procedures and guidelines that establish methods for the nssessment, evaluation, review, and ,
implementation activities associated with environmental and seismic )
qualification of Class 1E and Post Accident Monitoring Category 2 (PAM 2) I equipment at Calvert Cliffs. These procedures reflect the requirements of 10 CFR 50.49.
All Category I and 2 instrument loops will be reviewed in accordance with our J existing commitments.
For Category 1 variables, IEEE 344-1975 is used as the basis for seismic evaluation. Where seismic response curves have been developed for equipment resulting from testing, a review is made to assure that the test response spectra envelopes the required response spectra. If analysis is necessary, a load factor of 38 is assumed to account for the frequency excitation.
3.2.2 Category 3 Specific environmental qualification requirements were not included in our review of Category 3 variables. However, during the specification process for non-safety related electrical equipment BG&E considers the environmental conditions under which the equipment must operate in order to provide reasonable assurance that the equipment will function under all anticipated conditions.
3.3 Redundancy and Seoaration 3.3.1 Category 1 B G & E's separation criteria for the installation of safety-related electrical equipment is described in Section 8.5 of the Updated FSA R. This section presents BG&E design practices for the following:
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. Chcnnel identification
. Cable routing throughout the plant
. Cable routing in panels
. Separation of raceways
. Separation in penetration rooms These criteria assure that the minimum availability required during any DBA is met.
All Category 1 instrument loops were considered safety-related and weie evaluated in accordance with the applicable requirements.
3.3.2 Category 2 and 3 Where Category 2 and 3 vari.ibles have been classified as safety related for reasons other than R.G. 1.97, they have been irsta!!ed in accordance with separation requirements less stringent than for Category i vehile still providing for high signal reliability. BG&E's practices for instMhtion of non-safety related equipment are also described in Section 8.5 of the FSAR.
3.4 Power Sourgs 3.4.1 Category 1 BG&E's criteria for the design of the plant electrical power sources are described in Sections 8.1, 8.2, 8.3, and 8.4 of the Updated FSAR. Class IE electrical systems have been aesigned in accordance with "IEEE Criteria for Class IE Electric Systems for Nuclear Power Generating Stations," IEEE No.
308-1974.
All Category I loops are required to have power sources from buses satisfying the above criteria.
3.4.2 Category 2 and 3 Power sources for Category 2 and 3 instruments were reviewed for adequacy in light of their intended post-accident function. All Category 2 instruments were required to be supplied from a highly reliable power source. These were no specific requirements for Category 3 instrumentation. l l
3.5 Channel Availability 3.5.1 Category I l
For Type A variables the instrumentation channel will be available prior to l an accident except as provided in paragraph 4.11. "Exception" as defined in IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power
6 Generating Stations" or as specified in the technical specifications. For other Category i variables, the provisions will be similar to Category 2 variables.
3.5.2 Category 2 The out-of-service interval is based on the te:hnical specification requirements for the PAM function served by the instrumentation channel, where applicable.
3.5.3 Category 3 No specific provisions.
1 3.6 Ouality Assuranqn ;
3.6.1 Category I and 2 ,
l BG&E's Quality Assurance Policy is defined in Section IB of the Calvert !
Cliffs Nuclear Power Plant Updated FSAR. The program is responsive to the established requirements of the NRC and has been applied to the applicable activity for all safety-related equipment at Calvert Cliffs Nuclear Power Plant. In addition, a series of QA Procedures has been developed to implement the actions identified in the QA Policy.
All Category I equipment was considered safety-related and was evaluated in accordance with those requirements, where appropriate. Category 2 equipment i will also be considered safety-related, where appropriate. I 3.6.2 Category 3 No QA requirements apply to Category 3 instruments, liowever, normal BG&E l practices assure that high-quality equipment is procured and that t!'is equipment is installed and maintained in a manner consistent with its importance to plant operation.
3.7 Disolav and Recording BG&E's standard design practices are based upon providing continuous real-time displays on the main control panel (MCP) in a manner consistent with plant opereting requirements. In addition, seismically-qualified recorders are provided where essential to provide trending or transient information to the operator. in general, however, recorders on the MCP are not seismically qualified. This is considered consistent with the requirements of R.G. 1.97.
In addition to the MCP displays, PAM information is provided to engineering and off-site personnel via computer terminals located in the Technical Support Center (TSC) and Emergency Operations Facility (EOF). This provides additional assurance that trending information is available. Attachment C l compares the variables available at these terminals with PAM instrumentation provided in the main control room. The variables that are available to the SPDS via the plant computer are also shown on Attachment C. l 3.8 Rans BG&E's standard design practices are based upon the same requirements as those stated in R.G. 1.97. The appropriateness of the instruments ranges provided reflects this requirement.
3.9 Eauioment Identification No specific provisions exist at present to identify R.G. 1.97 instrumenta- l tion. Appropriate identification will be added and coordinated with our detailed control room design review (DCRDR).
3.10 Interfcces l BG&E's standard design practices provide for isolation devices when required to ensure proper operation and separation of all instrumentation loops. When instrument loops contain both qualified and non-qualified equipment, the isolation device is considered part of the qualified porticn. I 3.11 Servicina. Testing. and Ca!ibration Instrumentation is included in BG&E's planned maint?aance program. Testing
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is performed on instrument strings on a regular basis. The test points for the instrument strings are under administrative control (technical specification, maintenance procedure, or administrative procedure) to prevent unauthorized testing.
3.12 Iluman Factors l BG&E's DCRDR program includes a human factors review of control room I instrumentation. Any proposed plant upgrades will be made in accordance with I the schedule of modifications associated with our DCRDR submittal, j 3.13 Direct Measurement To the extent practicable, monitoring instrumentation inputs are from sensors that directly measure the desired variables.
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Table 1 Regulatory Guide 1.97, Rev. 3 Position Summary ITEM VARIABLE CATEGORY POSITION
- 1. Pressurizer Level 1 Upgrade indicators ar.d provide isolation devices 2 Pressurizer Pressure 1 No changes necessary 3 Pressurizer Temperature 3 No changes necessary 4 Pressurizer Spray Temp 3 No changes necessary 5 Pressurizer lieater Status 2 No changes necessary 1 6 SRV Position / Flow 2 No changes necessary l 7 Steam Generator Level 1 No changes necessary I ,
8 Steam Generator Pressure i Upgrade Indicator Power Sources )
9 Steam Generator Steam Flow 3 No changes necessary l 10 SIT Level 3 No changes necessary !
11 SIT Pressure 3 No changis necessary 12 SIT isolation Valve Pos 3 No changes necessary 13 Quench Tank Level 3 No changes necessary 14 Quench Tank Pressure 3 Changn range of indicator 15 Quench Tank Temperature 3 Change range of P t'cator 16 VCT Level 3 No changes necessai, 17 CVCS hiake-up Water 3 No changes necessary 18 CVCS hiake-up Boric Acid 3 No changes necessary 19 CVCS Letdown 3 No changes necessary 20 RWT Level 2 No changes necessary i 21 Condensate Storage Tank Lvl 1 No changes necessary l 22 Cntmt Sump Level- NR 3 No changes necessary 23 Cntmt Sump Level- WR I No changes necessary 24 Cntmt Sump Water Temp N/A Not applicable to CCNPP l 25 111 Radiation Liq. Tank Lvl 3 No changes necessary l 26 Radiation Gas Tank Press 3 No changes necessary 27 RCSTemperature(llOT) I hiodify channels to wide range 28 RCS Temperature (COLD) I hiodify channels to wide range 29 Subcooled hfargin 1 No changes necessary 30 Reactor Level hionitoring I hiodifications Complete 31 Core Exit Thermocouples I hiodification in progress 32 RCS Boron Concentretion 3 No changes necessary 33 RCP Status 3 No changes necessary
- 34 hiain Feedwater Flow 3 No changes necessary 35 Auxiliary Feedwater Flow 2 No changes necessary
- 36 liPSI Flow 2 No changes necessary 37 LPSI Flow 2 No changes necessary 38 Decay ifeat Removal Flow 2 No changes necessary 39 Decay lieat Removal Temperature 2 Upgrade TEs 1
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Table 1 l Regulatory Guide 1.97, Rev. 3 1 Position Summary ,
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ITEM VARIABLE CATEGORY POSITION 40 Boric Acid Charging Flow 2 Modification made; testing in progress 41 Neutron Flux 1 New WR channels to be installed 42 CEA Position 3 No changes necessary 43 Containment Pressure 1 Modification complete 44 Containment Temperature 2 Upgrade temperature elements 45 Cntmt H2Concentration 1 No changes necessary 46 Cntmt Heat Removal 2 Upgrade electrical installation 47 Cntmt Spray Flow 2 No changes necessary 48 Cntmt Isol. Valve Position 1 Installed 49 CCW to ESF, Temp. 2 Upgrade temperature elements 50 CCW to ESF, Flow 2 Upgrade transmitters 51 Fmergency Vent Damper Pos. 2 Add position indication where required 52 Status of Standby Power 2 Misc. wiring upgrade 53 RCS Radiation 3 No changes necessary 54 RCS Radiation Gamma 3 No changes necessary 55 Cntmt Area Radiation 1 No changes necessary 56 Condenser Off-gas Radiation N/A Not required 57 Main Vent Radiation / Flow 2 No changes necessary 58 Area Radiation 3 No changes necessary 59 Rad Monitor Safety RV's & 2 No changes necessary l Atmospheric Dump 60 Plant Release Points 3 No changes necessary l 61 Plant & Environment Rad. 3 No changes necessary 62 Meteorology 3 No cl.anges necessary 63 Accident Sample Analysis 3 No changes necessary I
l SRV System Relief Valve LPSI Low Pressure Safety injection SIT Safety injection Tank TE Temperatura Element VCT Volume Control Tank CEA Control Element Assembly CVCS Chemical and Volume Control System CCW Component Cooling Water RWT Refueling Water Storate Tank ESF Engineered Safety Features RCS Reactor Coolant System RVs Relief Valves RCP Reactor Coolant Pump WR Wide Range IIPSI High Pressure Safety Injection NR Narrow Range l
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Reg. Guide 1.97, Rev. 3 Implementation Plan FCR N1 DESCRIl TION IMP. SCHEDULE 80-1010 Reactor Vessel Level Monitoring Complete 82-150 Wide Range Ex-core Detector Complete - UI Upgrade Spring '89 Outage - U2 83-24 Upgrade kilR Outlet Temperature Complete - UI Indication Spring '89 Outage - U2 83-101 Provide Qualified Containment Complete Pressure Loop 83-1057 CET Upgrade Complete - Ul Spring '89 Outage - U2 84-1086 EQ Upgrade for RG 1.97 Complete - Ul Spring '89 Outage - U2 84-1087 hiisc Electrical Upgrades for Complete - UI RG 1.97 Spring '89 Outage - U2 4
84-1083 hiisc. Instrument hiodification for Complete - UI RG 1.97 Spring '89 Outage - U2 84-1091 Upgrade Diesel Generator Instrumentation Complete UI Cabling Spring '89 Outage - U2 84-1092 Upgrade 4 kv, 480V Class IE Switchgear Complete - UI Instrumentation Spring '89 Outage - U2 l 85-1023 Boric Acid Charging Flow Installed; Testing b i
- Indicatiori Progress 85-1051 Upgrade of Auxiliary Spray snd Charging Complete - Ul Line Isolation Schemes Spring '89 Outage - U2 87-11I hiodify Control Room Panel C06 to Complete - UI Incorporate R.G. 1.97 Items Spring '89 Outage - U2 87-112 Containment Heat Removal - Upgrade Comp! te - UI Transmitter and Power Supply Spring '89 Outage - U2
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ATTACilh!ENT A f f
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SUhthfARY OF SIGNIFICANT CHANGES l I
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DECEhiBER 1, 1984 RESPONSE TO NUREG-0737 l
BALTlhiORE GAS AND ELECTRIC COh1PANY l
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ATTACilMENT A
SUMMARY
OFSIGNIFICANTCilANGES The position statements for item I, Pressurizer Level; Item 2, Pressurizer Pressure; and item 7, Steam Generator Level were changed to remove the requirement for upgrading or replacing the containment electrical penetrations, since the penetrations for these instruments were re-evaluated and found qualified. Isolation devices to separate the safety-related instrumentation from the non-safety-related portion of the loop will be provided for item I so that the installation will conform with BG&E's criteria for safety-related circuits. Additional clarificat i on was added for item 5, Pressurizer lieater Status to describe the procedures for adding Mckup beaters after a Safety injaction Actuation Signal is received.
The evaluations fer item 10, Accumulator Tank Level; and item 11, Accumulator Tank Pressure were mnded to clarify the operation of the safety injection tanks in support of our po? on that a Category 3 rating is appropriate. Likewise for item 22, Narrow Range C' inment Sump Water Level, the evaluation was expanded to discuss the use of other in ..amentation to detect Reactor Coolant System leakage thus justifying the Category 3 rating. For item 24, Containment Sump Water Temperature, the expanded evaluation discusses why sump water temperature is not necessary for post-accident r.>.onitoring; and for Item 60, Plant Release Points, the expanded evaluation provides an explanation as to why the present instrumer.t range is sufficient for monitoring plant releases.
The position statement for Item 21, Condensate Storage Tar:k No. 12 Water Level, was changed to require no action. The no action position is based on NRC's review and acceptance of the seismic qualification of the Auxiliary Feedwater (AFW) System per Generic Letter 81-14. Additional justification is provided in the evaluation to item 21.
Equipment exposed to harsh environments for item 27, RCS Temperature (llot); Item 28, RCS Temperature (Cold); Item 29, Subcooled Margin; Item 43, Containment Pressure; Item 44, Containment Atmosphere Temperature; Item 46, lieat Removal by Containment Fan lleat Removal System; and item 49, Component Cooling Water Temperature to ESF were upgraded to meet 10 CFR 50.49, as applicable. Additionally, item 35, AFW Flow; Item 36, llPSI Flow; Item 37, LPSI Flow; Item 38, Decay llent Removal Flow; and item 47, l Containment Spray Flow were re-evaluated and found to meet 10 CFR 50.49 without '
requiring upgrades. A new action of providing one additional wide range channel per loop was also shown for item 28. Additional clarification was provided for item 36 i showing that the instrument range satisfies R.G. 1.97 requirements. l 1
On-going progress is reflected in position statements for item 31, Core Exit Thermo-couples; and item 40, Boric Acid Charging Flow. We continue to experience operational difficulty with the flow instrumentation on item 40. Testing is in progress to verify the instrument error and is scheduled to be complete in approximately three months.
Test results will be used to determine acceptability of existing instrumentation or used as a basis for design of a replacement unit in accordance with R.G. 1.97 requirements.
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A'ITACllMENT A l
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SUMMARY
OFSIGNIFsCANT CilANGES The existing design descriptions for item 32, RCS Soluble Boron Concentration; Item 54, Primary Coolant Gamma Spectrum; and Item 63, Post-Accident Sampling System (PASS) were changed to reflect the modified PASS. The modified PASS was found acceptable via a Safety Evaluation contained in a letter from D. H. Jaffe (NRC) to J. A. Tiernan (BG&E),
date' May 6,1986, and reflected the use of grab sample analyses for both the reactor coolant and con;ainment atmosphere versus in-line sampling m thods described previously.
A new commitment to install environmentally qualified equipment is shown for Item 39, Decay Heat Removal Temperature; Item 41, Neutron Flux; and Item 50, Component Cooling Water Flow to ESF due to new evaluations.
Although our previous submittal for Item 48 Containment Isolation Valve Position, indicated that no changes were necessary, we have upgraded the cabling to position switches for valves SV-517, 518, $19 and 5460 and have corrected the design description to state that only safety-related position switches are Class IE instead of all position switches as stated previously. All installation is complete and no further action is required for this item.
The Penetration Room Exhaust Eampers (Item 51, Emergency Ventilation Damper Position) are being replaced under 10 CFR 50.59 review with gravity operated dampers. The use of gravity campers provide more reliable operation in that the damper will operate as a check valve to prevent recirculation. In the prior configuration, if one fan failed during system operation, a recirculation path was created through the non-operating fan since both fans draw from a common inlet plenum and exhaust to a common discharge duct.
Because operation of these dampers is not dependent on any outside force or signal (e.g., they open upon start of penetration room exhaust fans), position indication is i not necessary or physically practical. Position switches and cabling to the ECCS and Spent Fuel Pool Exhaust Dampers located in harsh environments will comply with l
We have added a discussion concerning the use of IEEE 344-19i5 as the basis for seismic qualification of Category I variables.
The implementation schedules were changed to reflect the impact of adopting 24-month fuel cycles. For Unit 1, the startup following cycle 10 refueling outage was j July 1988, and for Unit 2, the startup following cycle 9 refueling outage is estimated j to be spring 1989. All of the FCRs in Table 2 of the Enclosure show equipment ;
installed for Unit 1. Five FCRs (i.e., FCR Nos. 83-24,53-101, 85-1051,87-111 and l 87-112) have been added to the implementation Plan, j 1
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4 ATTACilMENT B COMPARISON OF PLANT SPECIFIC VARIABLES WITil REGULATORY GUIDE 1.97, REVISION 3 BALTIMORE GAS AND ELECTRIC COMPANY l
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- EVALUATION SHEET FORMAT item 'of 63 CCNPP Units 1 & 2 Reg. Guide 1.97, Revision 3 Variable: Variable name as listed in Table 3 of R.G.1.97, Rev. 3 or BG&E's variable. name if more appropriate. The number in parenthesis is a sequence number.
Required Range: The range as listed in Table 3 of R.G. -1.97, Rev. 3.
Category: The Category as :ted in Table 3 of R.G.1.97, Rev. 3.
Existing Design: A description of the present CCNPP design for the instrumentation loop.
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Evsi..ation: A statement regarding the degree to which the instrumentation ,
meets the guidelines of R.G.1.97 and an assessment of the role of the variable in plant operation.
1 Position: A description of the specific actions that are proposed for
- CCNPP. [
Imp. Schedule: The FCR under which the necestasy changes will be accomplished, i
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CCNPP Units 1 & 2 l
. R.G.1.97, Revision 3 !
Item 1 of 63 Variable: Pressurizer Level (A-1 & D-II)
Required Range: Top to bottom Category: 1 Existing Design: Two separate channels are ;>'ovided with each covering a range extending from the bottom ot' the pressurizer to the _ code safety and electromagnetic relief valve nozzles. This corresponds to a i span of 0 to 360 inches of water, i Indicators are provided on panels C06 and C43 and one channel (switch selectable) with setpoint is recorded on C06. Both l channels are also input to the plant computer. l Power for each loop (with the exception of the recorder) is supplied from separate inverter fed, battery backed-up, Class IE i sources. !
The harsh environment equipment is qualified in accordance with the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation provided is adequate and sufficient for PAM except as noted above.
Poition: Safety-related digital indicators (with isolators) will be provided for each channel to improve reliability. The range will be O to 360 inches of water. An isolation device to separate the Category I safety-related (SR) instrumentation from the non-safety-related (NSR) portion of the loop will also be provided.
After this modification, the electrical installation will . be in accordance with BG&E's criteria for SR circuits. The power circuit to the recorder is satisfactory as installed, since the ;
source, although not IE, is highly reliable and backed-up by a diesel generator. l Imp. Schedule: FCR 87-111 l
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CCNPP Units 1 & 2 R.G. l.97, Revision 3 Item 2 of 63 i
I Pressurizer Pressure (A-2, B-7, B-ll, C-4, & C-9)
Variable:
Required Range: 0-4000 psig Category: 1 Existing Design: Two separate channels are provided with each covering a range of '
0 to 4000 psig.
l Indicators for Channel A are provided on panels CM and C43.
! Channel B is recorded on panel C06 and indicated on C43. Channel' i A is also input to the TSC. I Power for each loop is supplied from separate inverter fed, battery backed-up, Class IE sources and the electrical .,
i installation is in accordance with BG&E's criteria for safety l related circuits. j l l l
The harsh environment equipment is qualified in accordance with 1 the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation provided is adequate and sufficient for PAM.
Position: No changes are necessary. !
l Imp. Schedule: N/A l
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CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 3 of 63 Variable: Pressurizer Temperature (N/A)
Required Range: Not required by R.G.1.97 Category: 3 Existing Design: Two separate instrument loops are provided to measure pressurizer temperature. One loop measures the water phase temperature in the pressurizer and the other loop measures the surge line temperature. Primary elements are RTDs with a range of 0 to 650 degrees C.
Indicators with a scale of 0-700 degrees F are provided on pane!
C06. Both loops are also input to the phnt computer.
These instruments are used for operator guidance in the natural circulation cooldown procedures for limiting cooldown rate of the pressurizer to reduce thermal fatigue on equipment but serve no safety function.
Power for each loop is supplied from separate, highly reliable, non-Class IE instrumentation buses that are backed-up by diesel generators.
Evaluation: The instrumentation is adequate and sufficient for the intended post accident function.
Position: No changes are necessary.
Imp. Schedule: N/A
CCNPP Units 1 & 2
- R.G.l.97, Revision 3 Item 4 of 63 Variable: Pressurizer Auxiliary Soray Temperature (N/A)
Required Range: Not required by R.G.1.97 !
Category: 3 i Existing Design: One instrument loop is provided to measure pressurizer auxiliary spray temperature. The loop measures the temperature of the '
auxiliary spray feed from the regenerative heat exchanger. ;
An indicator with a scale of 0-600 degrees F is provided on C07 for the auxiliary spray temperature.
These instrument loops are used for operator guidance in the l natural circulation cooldown procedures to reduce thermal fatigue l on equipment but serve no safety function. ;
1 Power for each loop is supplied from separate, highly reliable, l
- non-Class IE instrumentation buses that are backed-up by diesel
' generators. '
Evaluation: The instrumentation provided is adequate and sufficient for the ,
intended post accident function, l l
Position: No changes are necessary. j Imp. Schedule: N/A 1
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. CCNPP Units 1 & 2
'. R.G.1.97, Revision 3 Item 5 of 63 ,
Variable: Pressurizer Heater Status (D-12)
Required Range: Electric Current I Category: 2 Existing Design: cts are installed on the feeders to the two proportional controllers (each consisting of 12 heaters). The other four banks of back-up heaters (each ..?tisting of twenty-four (24) .
, heaters) are only controlled in an "on-. ff' manner.
Ammeters with a range of 0-300 amps are provided on C06 for the two proportional heater banks. All six heater . banks have "on-off" indicating lights on C06 to indicate operating status.
After a Safety injection Actuation Signal - (SIAS), the back-up heaters can only be added manually (locally) by an operator.
Existing procedures prevent the operator from adding the heaters unt.il after the diesel loading has been verified and spare capacity exists in excess of the 300 KW required for the heaters.
Diesel loading is verified from the load center ammeters or the
, diesel KW meter; both have been evaluated with respect to R.G.
1.97.
No equipment in the instrumentation loop is - in a harsh !
environment.
Evaluation: While electric current is not measured for all heater banks, the
- existing design provides sufficient and adequate information for PA M. -
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. Position- No changes are necessary.
Imp, Schedule: N/A i
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-, '. R.G.1.97, Revision 3 '
item 6 of 63 '
Variable: Primary System Relief Valve Position / Flow (D-10) ;
Required Range: Closed-Not Closed Category: 2 i i
Existing Design: Acoustic monitors are installed downstream of the two Code _ Valves l and the two Power Operated Relief Valves to detect flow through the valves.- (
Digital indicators are provided on panels C06 and C31 to allew ,
the operator to detect flow through the valves. Additional indications of . rclief valve positions are provided through the D.L. and plant annunciator.
Power for each indicator on C31 is supplied from separate IE sources. Power for each indicator on C06 is supplied from highly _
reliable non-Class IE instrumentation buses that are . backed up by diesel generators. The electrical installation is in accordance with BG&E's criteria for Class IE circuits with the exception of the power cables and the indicators on C06.
The harsh environment equipment is "qualified' in accordance with the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation is adequate and sufficient for PAM.
Position- No changes are necessary.
Imp. Schedule: N/A
.. CCNPP Units 1 & 2 i' a
', R,G.1.97 Revision 3
- Item 7 of 63 i r
Variable: Steam Generator Level (A-4 and D-16) j Required Range: From tube sheet to separators !
Category: I ;
j Existics Design: Both steam generators are provided with four channels of level !
measurement with a range of -401 to 63.5 inches of water relative to the normal operating level. The tops of the steam separators
- are 391/4 inches above normal operating level (NOL) and the tube ,
sheet is 444 11/16 inches below NOL. t One channel is indicated and one channel is recorded on panel C04 and two channels are displayed on C43 for both steam generators.
Power for each channel is supplied . from separate inverter fed, battery. backed-up, Class IE sources ar.d the electrical installation is in accordance with BG& E's criteria for safety related circuits. I j
The harsh environment equipment is ' qualified
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d the requirements of 10 CPR 50.49 as applicable.
l l Evaluation: While the range is slightly less than required by R.G. l 97, it is j adequate and sufficient for PAM. l L
Position: No changes are necessary, i imp. St.Sedule: N/A l i !
l
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I 4 :
l 3
I !
A :
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CCNPP Units 1 & 2
', R.G.1.97, Revision 3 Item 8 of 63 I i
J Variable: Steam Generator Pressure (A-3 and D-17) [
i Required Range: Atm to 20% above lowest safety valve setting ,
a Category: 1 Existing Design: Both steam generators are provided with four channels of pressure measurement on the steam side with a range of 0 to 1200 psia. 1 The lowest safety valve can be set at 950 psia. I
! Indicators are provided on panel C03 for all four channels for both steam generators. One channel for both steam generators is input to the plant computer and the Technical Support Center. l 1 .
t' Power for each loop, with the exception of two indicators on i IC03, is supplied from separate inverter fed, battery backed-up, Class IE sources and the electrical installation is in accordance j with BG&E's criteria for safety related circuits.
! The harsh environment equipment is "qualified' in accordance with the requirements of 10 CFR 50.49 as applicable. l Evaluation: The instrumentation provided is adequate and sufficient for PAM.
- Position
- Indicators 1-PI-1013A and I-PI-1023A on ICO3 have been re-powered -
from separate Class lE sources.
Imp. Schedule: FCR 84-1087 k
i <
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1 i
j
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CCNPP Units 1 & 2
[
'. R.G.1.97, Revision 3 Item 9 of 63 ,
t Variable: Main Steam Flow (D-18) j Required Range: No Range Specified !
l t Category: 2 Existing Design: One instrument loop is provided for each steam generator to measure flow over a range of 0 to 6x 10E+6 LB/HR This ,
corresponds to the design flow for the steam generators. One ;
indicator and one recorder is provided for each steam generator i l on panel C03 with a scale of 0 to 6 x 10E4 LB/HR. .
i Power for each loop is supplied from separate, inverted fed,
! battery backed-up Class IE sources. The installation - is in ,
l accordance with BG&E's criteria for non-safety-related circuits.
Evaluattor: The equipment provided meets the guidelines of R.G.1.97. However, main steam flow is not considered a significant parameter in the CCNPP EOPs. I Position: A downgrade to a Category 3 indication requirement is appropriate for this parameter. No changes are necessary.
Imp. Schedule: N/A l
s h
I I
- CCNPP Units 1 & 2
', R.G.1.97, Revision 3 Item 10 of 63 1
Variable: Accumulator Tank (SIT) Level (D-3)
Required Range: 10% to 90% Volume l Category: 2 1
Existing Design: One instrument loop is provided for each of the four SITS to ,
measure level over a 333 inch range. This corresponds to 5% to 95% of the tank volume.
Two indicators are provided on panels C08 or C09 for each tank to
- indicate Wide Range (0 to 336 inches) or Narrow Range (184 to 202 l inches) level.
Power for each loop is supplied from highly reliable non-Class IE instrumentation buses that are backed-up by a diesel generator.
The installation is in accordance with BG&E's criteria for non-safety-related circuits.
The harsh environment instruments are not "qualified'.
Evaluation: The equipment does not meet the guidelines of R.G, 1.97. 110 wever, SIT level is only used for pre-accident indication of the status of SITS to assure that the SIS is prepared to serve its safety function.
The four separate and independent safety injection tanks are each ,
connected to one of the four reactor vessel cold leg pipes. The l driving head for water injection is provided by nitrogen gas l pressure within the tanks at a minimum pressure uf 200 psig. As )
the reactor coolant system pressure falls below tank pressure, check valves open in the line connecting each tank to the reactor coolant system and the contents of the tank are transferred to the reactor vessel. The tanks operate as a passive stored-energy safety feature; therefore, no outside power source, signal, or operator action is required for their operation during a design !
basis accident. The level and pressure instruments are only used i to monitor the status of the tanks during normal operation to l assure that the safety injection system is prepared to serve its i safety function. I l
We consider this instrumentation Categnry 3 at CCNPP (diagnostic j instrument to monitor the operation of the safety injection '
systems). Knowledge of accurculator discharge is not useful to l the operator. The accumulators discharge very early in the event in a large break LOCA. Even if the operators were aware of the failure of an accumulator to discharge, they could not take l l action quickly enough to make a difference in the outcome of the i event. Since the operator is relying on Type A and B variables to indicate whether plant safety functions are being accomplished, and since this instrumentation does not support
(
l
CCNPP Units I & 2 c
' R,G.1.97, Revision 3 1 I
Item 13 of 63 i Page 2 !
T operator actions, we- have downgraded it from Category 2 to t Category 3 (key to backup or diagnostic).
Position: A downgrade to a Category 3 Indication requirement is appropriate. No changes are necessary.
l Imp. Schedule: N/A i l
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- CCNPP Units 1 & 2
^' R.G. l.97, Revision 3 ;
i .
1 !
Item 11 of 63 1
Variable: Accumulator Tank (SIT) Pressure (D-3) l Required Range: 0 to 750 psig .
- Category
- 2 l
1 l j Existing Design: One instrument loop is provided for each of the four SITS to :
! measure pressure over a 0 to 250 psig range. Relief valves on l
' the tank are set to relieve at 250 psig, i Two indicators for each of the four tanks are provided on either panels C08 or C09 to indicate Wide Range (0 to 250 psis) or i Narrow Range (200 to 240 psis) pressure.
4 Power for the WR loop is supplied from highly rsliable non-Class IE instrumentation buses that are backed up by a diesel
- generator. The installation is in 'accordance with BG&E'r ;
~
j criteria for non-safety-related circuits.
The harsh environment instruments are not ' qualified".
J
] Evaluation: The evaluation is the same as that for item 10. Accumuhtor Tank ,
(SIT) Level (D-3). l Position: A downgrade to a Category 3 indication requirement is I appropriate. No changes are necessary.
. Imp. Schedule: N/A 4
1 1
i l i
1 4
1 4
l 1
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1
. CCNPP Units 1 & 2 !
- . R.G. l.97, Revision 3 i
Item 12 of 63 i
Variable: Accumulator Tank Isolation Valve Position (D-4) i Required Range: . Closed or Open Category:
2 ,
I 1
Existing Design: Open/ Closed indicator lights are provided on C03 or C09_ to ;
indicate valve status.
l The indicators are powered from Class IE buses that are backed up ;
by diesel generators.
Evaluation: The instrumentation provides only pre-accident information to assure that the SIS is prepared to serve its safety function. ,
- Pos' tion
- A downgrade to Category 3 is appropriate. No changes are-necessary. .
- imp. Sch?dule
- N/A ,
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- CCNPP Units 1 & 2
~' R.G.1.97, Revision 3 i Item 13 of 63 Variable: Quench Tank Level (D-13)
Required Range: Top to Bottom Category: 3 Existing Design: One instrument loop is provided to measure level over a 48 inch range that extends from 6 inches below the top to 6 inches from the bottom of the tank. This corresponds to 4% to 96% of the tank volume. -
One indicator is provided on panel C06. The level is also input l to the plant computer. I i Power is supplied from highly reliable non-Class IE instrumenta -
tion buses that are backed-up by diesel generators.
Evaluation: While the range is less than required, the instrumentation provided is adequate and sufficient for the intended PAM function.
Position: No changes are necessary.
Imp. Schedule: N/A I
t s
l t
4
- CCNPP Units 1 & 2 R.G.1.97. Revision 3 Item 14 of 63 l Variable: Quench Tank Pressure (D-15)
Required Range: 0 to design pressure Category: 3 t Existing Design: One instrument loop is provided to measure pressure over a 0 to 25 psig range. The rupture disc pressure is 100 psig.
One indicator is provided on- panel C06 and the pressure is also !
input to the plant computer. I Power for the loop is supplied from a higi:ly reliable non-Class IE instrumentation bus that is backed up by a diesel generator.
Evaluation: The instrumentation is cat in accordance with the guidelines of R.G.1.97.
Position: A wide range indicator (0 to 100 psis) will be installed in [
addition to the existing narrow range indicator (0 to 25 psig). '
imp. Schedule: FCR 84-1088 1
4 1
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CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 15 of 63 i
) i
- Varia'ule
- Quench Tank Temperature (D-14) ,
Required Range: 50 to 750 degrees F ,
Category: 3 Exis'ing Design: One instrument loop is provided to measure temperature with a dual element RTD with a range of 0 to 650 degrees C.
One indicator with a range of 0 to 300 degrees F is provided on panel C06 and the RTD is also input to tha. plant computer with a l rarse of 32 to 850 degrees F.
, Power for the loop is supplied by a highlv reliable non-Class IE instrumentation bus that is backed up by a diesel generator.
Evaluation- The range is less than required and is hot in accordance with the '
guidelines of R.G.1.97. With a rupture dis; pressure of 100 psig 3
a maximum saturation temperature of 338 degrees F is possible and ,
the indicator range should cover this. '
Position: The Indicator will be re-calibrated and tie scale changed to :
cover 50 to 350 degrees F.
Imp. Schedule: FCR 84-1088
]
1
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1 I
i 1
4
. CCNPP Units 1 & 2 )
R.G.1.97, Revision 3 Item 16 of 63 Variable: Volume Control Tank Level (D-26)
Required Range: Top to Bottom !
Category: 2 i
Existing Design: One instrument loop is provided to measure level over a 120 inch range that extends from ?! 3/8 inches above the bottom to 26 5/8 inches below the top. This corresponds to 8% to 86% of the tank l l volume.
4 One indicator is provided on panel C07 with a range of 0 to 120 inches and the level is also input to the plant computer. l Power for the loop is supplied by a highly reliable non-Class IE ,
instrumentation bus that is backed up by a diesel generator.
The harsh environment equipment is not "qualified'.
1 Evaluation: The instrumentation does not meet the guidelines of R.G. 1.97.
liowever, the volume control tank level indication is only used during normal operation. The RCS letdown line and the VCT '
make-up to the RCS are isolated by control valves in the event of '
j Safety injection Actuation.
i Position: A downgrade to Category 3 indication requirements is appropriate, i No changes are necessary.
Imp. Schedule: N/A f
4 d
4 4
I f
b I 4
j I .
. CCNPP Units 1 & 2 i R.G.l.97, Revision 3 Item 17 of 63 Variable: CVCS Make-up Flow-In (Demin. Water),(D 26) ;
Required Range: 0 to 110% Design Flow l Category: 2 Existing Design: The instrument loop provides control room indication of 0-150 gallons per minute. The devan flow is 160 gpm. The percentage
{
flow monitored is 0-94%. i An indicator and a flow recorder are on panel C07 with annunciation and plant computer input.
I Power for the loop is provided by reliable non-Class !E l instrumentation bu': that is backed up by a diesel generator. The :
Installation is in accordance with BG&E's criteria for non-safety '
related circuits.
The harsh environment is not "qualified" Evaluation: The equipment does not meet the guidelines of R.G. 1.97 for Category 2. Ilowever, this equipment is not required for PAM l since the make-up flow is isolated to the VCT which in turn is I isolated from ' the RCS in the event of a Safety injection ,
Actuation. The instrument loop only monitors flow to the VCT not l to the RCS. l Position: A downgrade to Category 3 indication requirements is appropriate. l i
No changes are necessary, imp. Schedule: N/A 1
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. ' CCNPP Units 1 & 2 l i R.G.1.97, Revision 3
, r 5
item 18 of 63 ;
Variable: CYCS Make-up Flow-lu (Boric Acid), (D-26)
Required Range: 0 to 110% Design Flow Category: 2 <
s Existing Design: One instrument loop is provided to measure boric acid make-up
. flow to the VCT over a range of 0-30 gallons per minute. This ,
, corresponds to 0-150% design flow.
- One indicator is provided on control room panel C07.
s Power for the loop is provided by a reliable non-Class IE instrumentation bus that is backed up by a diesel generator. The
! installation is in accordance with BG&E's criteria for non-safety related circuits.
. The harsh environment equipment is not "qualified". ;
Evaluation: The eaulpment does not meet the guidelines of R.G. l.97. liowever. l boric acid make-up flow to the VCT is isolated in the event of .
- Safety injection Actuation. This instrument is only used during j normal operation and is not required for PAM.
4 Position: A downgrade to Category 3 indication requirements is appropriate.
No changes are necessary.
4 Imp. Schedule: N/A 1 l j
l
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4 4
l 1
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l 1
4 1
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CCNPP Units 1 & 2
. ' R.G.1.97, Revision 3 Item 19 of 63 Variable: CVCS Letdown Flow (D-27)
Required Range: 0 to 110% Design Flow Category: 2 Existing Design: One instrument loop is provided to monitor the letdown flow over a range of 0-150 spm. This corresponds to 0-110% of design flow.
One indicator is provided on control room panel C07 and a plant computer input is also provided.
Power for the loop is provided from a reliable non-Class lE instrumentation bus that is backed up by a diesel generator. The installation is in accordance with BO&E's criteria for non-safety related Circuits.
The harsh environment equipment is not
- qualified *.
Evaluation: The letdown line flow instrumentation does not meet the guidelines of R.G. l.97. However, it is only used for normal plant operation. In the event of Safety inhetion Actuation, the letdown line is isolated and this instrument is not required for PAM.
Position: A downgrade to Category 3 indication requirements is appropriate.
No changes are necessary.
Imp. Schedule: N/A
)
l 1 . CCNPP Units 1 & 2 i
. i R.G. l.97. Revision 3 l Item 20 of 63 Variable: Refueling Water Storage Tank Level (D 8) 1
- Required Range
- Top to bottom l
Category: 2 l
) Existing Design: Two separate instrument loops (wide range and narrow range) with '
i indicators are provided. The narrow range covers a span of 444 ,
inches to 468 inches with indication of C08. Indication on C09 l is for the wide range which spans 18' above the bottom to 12' below the top of the tank. ,
4 l Two computer inputs and i Tech Support Center computer input are j provided. .,
Power for both loops is supplied from highly reliable non-Class -
! IE instrumentation buses and the installation is in accordance '
I with BG&E's criteria for non-safety related circuits. l 1 l i The equipment located in a harsh environment is environmentally ;
i qualified. !
1 l Evaluation: The wide range instrumentation provided is adequate .and -
l sufficient for PA M. The narrow range is not necessary for
. R.G. l.97.
,. y Position: No changes are necessary.
l ,
j i imp. Schedule: N/A l I
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. CCNP' l'ults 1 & 2 i R.G. 1.91, Revision 3 l l
Item 21 of 63 i a i Variabe: Condensate Storage Tank No.12 Water Level (D-21, A-8) l Required Range: Plant Specific l Category: 1 ,
! 1 Existing bsign: Two separate and redur. dant instrument loops provide a continuous monitoring of the level from 12 inches above the bottom of the ,,
t tank to the top of the tank (a Span of 38 feet). ,
Indicators are provided on panels C04 and C43 for each loop, i
Additional indication is provided to de Tech Support Center .
Computer.
- Power for each loop is supplied from separate inverter fed, 4
battery backed up class IE sources. The electrical installation ;
is in accordance with BG&E's criteria for non-safety-related circuits. Cable to the level transmitter is routed through the pipe tunnel outside the tank area and through the turbine {
building, i No equipment is located in a harsh environment.
Evaluation: The electrical installation was reviewed by NRC as part of BG&E's submittsls addressing AFW modifications per Generic Letter 81-14 Water level is checked and logged every four hours locally and in ,
i the control room, if AFW is lost during an event, an operator >
checks the local level indication. That operator will switch ;
l from CST 12 to CST 11 (21) if both level indications are lost or !
if they do not agree with the CR indication.
i in loss of power to the level transmitters, the indicator fails !
- low and is alarmed in the control room. An operator will then l switch from CST 12 to CST 11 (21). !
l Position: T1.e wide range instrumentation is considered sufficient and no ;
! action is required. ;
! Imp. Schedule: N/A i i
] l i
4 :
i !
f
_ - - _ - - _ . . - ..__ _ -, . . - , . _ _ . _ . _ . _ . . _ , - _ , - . . . _ . - - _ _ , . _ - - - ~ - - _ . - - _ . -
CCNPP Units 1 & 2
' R.G.1.97, Revision 3 i
Item 22 of 63 ;
i Variable: Containment Sump Water Level, Narrow Range (B-12 & C-6) i Required Range: Sump Category: 2 ,
Exi* ting Design: Two separate instrument loops are provided to measure water level l in the containment sump over a 0 to 30 u'bh range.
One indicator per loop is provided with one loop indicator on C08 and the other on C09.
wer for the loops is provided from separate highly reliable aon-Class IE instrumentation buses that are backed up by diesels. ;
The installation is in accordance with DG&E's criteria for non-safety related circuits. .
i The harsh environment instruments are not qualified. i Evaluation: The equipment does not meet the guidelines for Category 2.
However, this equipment is used only during normal operation. }
At CCNPP, pressurizer level in conjunction with cycling of the charging pumps alerts operators to excessive RCS leakage.
l During steady state power operatior.s, leaks would be indicated as i follows: ;
Leak rate less than 11 gpm. ,
The maximum allowable total leak rate for identified plus unidentified leaks is 11 gpm. -
Leak Rate 11-55 gpm.
Le;kage in this range is indicated by the first backup charging pump cycling on and off to maintain pressurizer level between -4.1" and -9.3". Time response for a 33 gpm i leak:
5.57 minutes to start tne first backup pump.
i Leak rate 55-99 apm.
Leakage in this range is indicated by . the second backup !
charging pump cycling on and off to maintain pressurizer !
level $>etween -6.5" and -13.5". ;
Time response for a 77 gpm leak: :
2.02 reinutes to :. tart the first backup pump. !
4.84 minutes to start the second backup pump.
t l
1
CCNPP Units 1 & 2 R.G. 1.97, Revision 3 Item 22 of 63 Leak rate greater than 99 gpm.
Ler.kage in this range is indicated by all three charging
} pumps running while pressurizer level continues to decrease, and a low level alarm.
Time response fo a 121 gpm leak:
1.23 minutes to start the first backup pump.
2.17 minutes to start the second backup pump.
3.18 minutes to low level alarm.
Position: A downgrade to Category 3 indication requirements is appropriate.
No changes are necessary.
Imp. Schedule: N/A l
l
CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 23 of 63 l
Variable: Containment Sump Water Level, Wide Range (B 12 & C-6) ,
Required Range: Plant Specific Category: 1 j Existing Design: Two separate and redundant instrument loops are provided to measure level from 9 inches above the containment floor to 4 feet above the 600,000 gallon level. ,
i Two indicators are provided on panel CIO, one for each loop with an indicating range of 0 to 120 inches.
Power for the loops is provided from separate inverter fed, battery backed up class IE sources. The installation is in accordance with BG&E's criteria for safety related circuits.
The harsh environment equipment is "qualified" in accordance with the requirements of 10 CFR 50.49 as applicable.
1 Evaluation: The instrumentation provided is adequate and sufficient for PAM. '
Positium No changes are necessary.
Imp. Schedule: N/A l l
l l
l 4 i
CCNPP Units 1 (. 2 R.G.1.97, Revis!oa 3 Item 24 of 63 Variable: Containment Sump Water Temperature (D-25)
Required Range: 50 to 250 degrees F
\
Category: 2 ,
Existing Design: No instrumentation exists f Evaluation: The guidelines of R.G. 1.97 are not met. However, this variable l is not used la the management of a design basis accident and is not rcq'u ired for PAM.
As stated in ocr Final Safety Analysis Report, Net Positive l
Suction Head (NPSH) is ensured for the HPSI pumps because the containment sump water level is +15 feet plant elevation at the time of -RAS (Recirculation Actuation Signal) and the cer':r line of the pump is at (-)12 feet plant elevation. Minimum NPSH requirements are not dependent on the watef temperature in the containment :: ump, therefore this variable is not used in the management of a design basis accident and is not required for post-accident monitoring.
At CCNPP, water taken from the containment sump passes through shutdown cooling (SDC) heat exchangers before flowing to the containment spray header nozzles. The system is monitored by SDC l
system flow and SDC heat exchanger outlet temptrature instruments. The effectiveness of the spray system depends on the difference between the spray water temperature at the nozzle and the containment ' atmosphere temperature. Tne water temperature at the containment or at the SDC heat exchanger inlet is only an indirect measure of containment heat removal arid has the potential to confuse the operators. Since we consider both SDC system flow and SDC heat exchanger outlet temperature Category 2 instruments, we already satisfy the basis given in R.G.
1.97 (monitor the operation of the containment cooling synem) without providing instrumentation for containment sump temperature.
Position: No instrumentation is necessary.
Imp. Schedule: N/A
CCNPP Units 1 & 2
- R.G.1.97, Revision 3 Item 25 of 63 Variable: High Level Radioactive LiquM Tank Level (D-31)
Required Range: Top to Bottom Category: 3 Existing Design: The two Reactor Coolant (RC) Waste Receiver Tanks and two RC '
Waste Monitor Tanks are each provided with one instrument loop to measure level over a 0 to 32 ft span. This covers a range from 73 inches above the bottom to 60 inches below the top. This corresponos to 93% of the tank volume.
Indicators with a range of 0-32 ft. are provided for each tank in the MCR on panel C33 plus each level is input to the plant l computer. '
Power for each loop is supplied from a highly reliable non-Class IE instrumentation bus that is backed up by a diesel.
Evaluation: Wh!!c the range does not meet the guidelines stated in R.G.1.97, the instrumentation provided is adequate and sufficient for PAM.
Position: No changes are necessary.
Imp. Schedule: N/A
CCNPP Units 1 & 2 R.G.1.97, Revision 3 Ite.a 26 of 63 Variable: Radioactive Gas 11oldup Tack Pressure (D-32)
Required Range: 0 to 150% design pressure Category: 3 Existing Design: The three hoidup tanks and one surge tank that are common to both Ul and U2 are each provided with one instrument loop to measure pressure. Holdup tank pressure is measured over a range of 0 to 150 psig with a design prasure of 150 psi. Ifoldup tanks relieve to the surge tank at 150 psig, which is measured over a range of .
O to 100 psig with a design pretsure of 50 psig.
Indicators are provided on C33 for all tanks and the holdup tank l pressures are also input to the plant computer. '
Evaluation: While the ran2e does not meet the guidelines stated in R.G.1.97, and the oniy MCR display is via the plant computer, the l instrumentatic.n provided is adequate and sufficient for 'PAM.
Position: No changes are necessary.
Imp. Schedule: N/A
- , - - - , ,, , , . , . . . , - _ . , - . , _ . . - - , , , , ,,, _ -....,,,e., , ,-
l CCNPP Units 1 & 2 1
- R.G.1.97, Revision 3 Item 27 of 63 Variable: RCS Hot Leg Water Temperature (A-5 & B-5)
Required Range: 50 to 700 degrees F Category: 1 Existing Design: Wide range RCS Hot Leg Temperature is currently available for display via the Sub-cooled Margin Monitor Display. Narrow range indicators (515 to 615 degrees F) are also provided and one narrow range channel is recorded. In addition, two channels of wide range indicators are available on the auxiliary shutdown panel.
Power for the loops is provided from separate inverter fed battery backed up Class IE sources. The wide range installation is in accordance with BG&E's criteria for safety related circuits.
]
The harsh environment equipment is qualified in accordance with the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation does not met t the stated guidelines of .
R.G. 1.97. I l
Position: Loops TE-ll2HC and TE-122HD currently supplying the reactor )
protective system will be modified via the installation of l dual-output transmitters and modified indicators to provide one additional wide range channel per loop. Two wide range channels will be recorded on panel C06 l l
i Imp. Schedule: FCR 84-1088,87-111 I
CCNPP Units 1 & 2
. R.G. 1.97, Revision 3 Item 28 of 63 .
l Variable: RCS Cold Leg Temperature (A-6 & B-5) 1 Required Range: 50 to 700 degrees F Category: 1 Existing Design: Wide range RCS Cold Leg Temperature (0 to 600 dcgrees F) is displayed on a digital indicator that receives an auctioneered signal from RFS transducers and also on the Subcooled Margin Monitor. The temperature is also recorded. Power for the loops 3s provided from separate inverter fed battery backed up Class IE sources. The installation is in accordance with B G & E's criteria for safety related (SR) circuits.
The harsh environment equipment is qualified in accordance with the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation does not meet the stated guidelines of ,
R.G. 1.97. i Position: Loops TE-Il2CC and TE-122CD currently supply the reactor protective system will be modified via the installation of l dual-output transmitters and modified indicators to provide one j additional wide range channel per loop. Two wide range channels l will be recorded on panel C06.
]
Imp. Schedule: FCR 84-1088,87-111 l l
l 1
l l
1
6 CCNPP Units 1 & 2
'- R.G. 1.97, Revision 3 Item 29 of 63 Variable: Degrees of Subcooling (A-7 and B-10)
Required Range: 200 degrees F subcoc:ing to 35 degrees F superheat Category: 1 Existing Design: Two redundant instrument loopt are provided to determine subcooled margin. Hot and cold leg temperatures are measured over a range of 212 to 705 degrees F and RCS pressure is measured over a range of 15 to 3208 psia. Subcooled margin is calculated over a range of 100 to O degrees F of subecoling.
Indicators are provided on panel C05 that display either temperature or pressure margin.
Power for each loop is supplied from separate inverter fed, battery backed up, Class IE sources. The electrical installation is in accordance with BG&E's criteria for safety related circuits.
The harsh environment equipment is qualified in accordance with l the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation does not meet all of the guidelines for R.G. !
1.97. The range provided, however, is adequate to meet the needs l of our EOPs. RCS pressure and temperature indications allow a !
manual calculation of the saturation margin over a greater range if required.
Position: No changes are necessary.
Imp. Schedule: N/A I
CCNPP Units 1 & 2
, '. R.G.1.97, Revision 3 Item 30 of 63 Variable: Coolant Inventory (B-9)
Required Range: Bottom of hot leg to top of vessel j
Category: 1 l
i Existing Design: No provisions previously existed to monitor coolant inventory (level) in the reactor vessel. A Heated Junction Thermocouple (HJTC) react 0r vessel level measuring system based on Combustion Engineering seneric design is now provided. The main control board display consists of eight lights per channel to reflect the l status of each pair of HJTC. A recorder provides a permanent trer.d history of reactor level. The Reactor Vessel Level Mor.itoring System (RVLMS) is designed to meet the intent of
, R.G.1.97 in accordance with Section 3 of this submittal.
l Evaluation: The instrumentation recently installed is adequate and sufficient for PAM.
l Position: No further changes are necessary.
l l
l Imp. Schedule: FCR 80-1010 (Complete) l 1
l l
l l
l
. i l
CCNFP Units 1 & 2 R.G. I 97, Revision 3 l
Item 31 of 63 Variable: Core Exit Temperatures (B-8 and C-1)
Required Range: 200 to 2300 degrees F Catee,ory: 1 Existing Design: Core exit temperatures are mea:;ured by type K thermocouples included with the forty-five (45) in-core detector assemblies.
Temperatures are input to the plant computer with a range of 32 1 to 2300 degrees F. ]
The harsh environment equipment has not been evaluated as part of our EQ program. ;
i Evaluation: The existing instrumentation for the PAM of core exit ;
temperatures does not meet the guidelines of R.G. 1.97. j Position: Per our June 19, 1985 letter from Lundvall to Butcher, we are
' committed to provide four environmentally qualified CET channels per quadrant for Unit I by Cycle 10 start-up (July 1988 -
completed) and Unit 2 by Cycle 9 start-up (Spring 1989).
Additional qualified channel will be provided to replace existing non-qualified channels en an as-fail basis. The cabling, display hardware and other electronics were iiistalled on Unit I prior to Cycle 9 start-up and have satisfactorily passed functional testing prior to Cycle 10 start-up.
Imp. Schedule: FCR 83-1057 I l
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. 1 CCNPP Units 1 & 2 l R.G.1.97, Revision 3 Item 32 of 63 Variable: RCS Soluble Boron Concentration (P-3)
Required Range: 0 to 6000 ppm ]
Category: 3 !
l Existing Design: A system is provided with a range of 0 -5000 ppti, which becomes l inoperable after a SIAS since it takes its sample from the letdown line. A recorder with a range of 0-3200 ppm is provided i on panel C07 and indicators are provided on C06. A grab sample !
can also be obtained from the NSSS sample sink and analyzed using i a variation of the ASTM specified sampling technique. l Evaluation: The equipment meets the guidelines of R.G.1.97 with the exception of range. The range provided, however, adequately covers the '
anticipated range of Boron concentration. ,
1 Position: No changes are necessary. !
Imp. Schedule: N/A i i
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l CCNPP Units 1 & 2
' - R.G.1.97, Revision 3 j l
Item 33 of 63 Variable: Reactor Coolant Pump Status (D-9)
)
Required Range: Motor Current ,
l Category: 3 l Existing Design: The status indication for RCP motor current is provided by one ammeter for each motor covering a range of 0 to 400 amperes with a ' normal running current of 200 amperes. The indicators are located on panel C06. The instrumentation derives power from the monitored source.
Evaluation: The instrumentation is adequate and sufficient for PAM.
Position: No changes are necessary.
Imp. Schedule: N/A i
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. s CCNPP Units 1 & 2
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R.G.1.97, Revision 3 Item 34 of 63 Variable: Main Feedwater Flow (D-19)
Required Range: 0 to 110% design flow Category: 3 l
Existing Design: One channel per - steam generator feedline is provided covering a range of 0 to 6 x 10E+6 lbs/hr.
Indication of Feedwater Flow is provided by an indicator / con-l troller and a recorder for ea:h feedline. In addition both loops l
are input to the Plant Computer and the Technical Support Center Computer.
Power is provided from inverter fed, battery backed up Class IE sources. The installation is in accordance with - BG&E's criteria
! for non-safety related circuits.
l Evaluation: The instrumentation is adequate and sufficient for PAM.
1 Position: No changes are necessary.
l Imp. Schedule: N/A l
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CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 35 of 63 Variable: Auxiliary Feedwater Flow (D-20)
Required Range: 0 to i10% design flow Category: 2 Existing Design: One channel of flow instrumentation per feedline is provided with a range of 0-750 GPM for the steam driven pumps and 0 to 500 GPM for the motor driven pumps. !
Indication is provided by indicator / controllers on the Main Control Panels and by indicators at the Auxiliary Shutdown Panel.
The instruments are powered from inverter fed, battery backed-up class IE sources. The installation is in accordance with B G & E's ,
criteria for safety related circuits. 1 That instrumentation located in a harsh environment is qualified per 10 CFR 50.49.
Evaluation: The installed instrumentation is adequate end sufficient for PAM.
Position: No changes are necessary.
Imp. Schedule: N/A i
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1
', CCNPP Units 1 & 2
. R.G.1.97, Revision 3 Item 36 of 63 Variable: llPSI Flow (D-6)
Required Range: 0 to 110% design flow Category: 2 Existing Design: Four separate instrument loops are provided, one for each train of safety injection, to measure High Pressure Safety Injection flow. The indicated range is 0 to 300 gpm.
Indication is provided at panels C0g and C09 and all four loops are input to the Technical Support Center Computer.
Power for each loop is supplied from highly reliable non class IE !
instrumentation buses that are backed up by diesels. The electrical installation is in accordance with BG&E's criteria for non-safety related circuits.
The harsh environment equipment is qualified in accordance with l the requireraents of 10 CFR 50.49 r.s applicable.
Evaluation: The instrumentation provided is in accordance with the guidelines i of R.G. 1.97. l l
The design ficerate is 345 gpm; therefore, the range is less than i 110% design flow.
The liigh Pressure Safety Injection (IIPSI) System contains three llPSI pumps. The discharge piping from the three pumps combine at a common main header and a common auxiliary header. Each header then branches off into four injection pathways to the reactor coolant system. Flow is measured ori cach of the four injection pathways, not at the pump discharge. Upon receipt of a safety l injection actuation signal two pumps start automatically with the flow distributed between the four injection paths. Based on accident analysis and flow calculations the maximum flow in each leg is expected to be approximately 200 gpm. This is well within the 0 to 300 gpm range of the existing instrumentation.
Position: No modifications are required.
Imp. Schedule: N/A
- CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 37 of 63 Variable: Flow in LPSI System (D-7)
Required Range: 0-110% design flow Category: 2 Existing Design: One instrument loop is provided to measure the total LPSI flow to the RCS over a range of 0-8000 GPM. The two LPSI pumps each have a design capacity of 3000 GPM for a total design capacity of 6000 GPM. In addition, one instrument loop is provided for each of' the four RC loop cold leg LPSI feeds over a range of 0-2500 GPM.
Indicators for all five flow measurements are provided on either panel CO8 or CO9 and all signals are also input to the TSC. l Power for each loop is supplied from highly reliable non-Class IE instrumentation buses that are backed up by diesels. The ,
electrical instal lation is in accordance with BG&E's criteria for l non-safety related circuits.
The harsh environment equipment is qualified in accordance with I the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation provided is in accordance with the guidelines l ,
of R.G. 1.97.
l Position: No changes are necessary. i Imp. Schedule: N/A l
. =. .- . . .
', CCNPP Units 1 & 2
. R.G.1.97, Revision 3 )
1 1
Item 38 of 63 j i
1 Variable: RHR System Flow / Decay Heat Removal Flow (D- 1)
Required Range: 0-110% design flow Category: 2 Existing Design: Decay heat removal is provided by the shutdown cooling system )
which utilizes the two LPSI pumps and two shutdown cooling beat exchangers.
Instrument loops provided for LPSI flow measurement (see item 37) provide the required flow indications.
Evaluation: The instrumentation is in accordance with the guidelines of R.G.
1.97.
Position: No modifications are necessary.
Imp. Schedule: N/A l l
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. . 1 CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 39 of 63 1
Variable: RHR Heat Exchanger Outlet Temperature (D-2) i Required Range: 40 to 350 degrees F Category: 2 Existing Design: Decay heat removal is provided by the- two shutdown cooling heat <
exchangers. The outlet temperatures of both exchangers are me.asured with RTDs with a range of 0-650 degrees C. l A recorder with a scale of 0 to 400 degrees F is provided on )
panel C09. Both loops are also input to the plant computer. l j i
The instruments are powered by highly reliable non class IE l instrumentation bus that is backed up by a diesel. .The )
electrical installation is in accordance with BG&E's criteria for non-safety related circuits. The temperature elements are not qualified per 10 CFR 50.49.
Evaluation: The instrumentation provided does not meet the guidelines of R.G. 1.97.
Position: The temperature element will be upgraded to SR and 10 CFR 50.49.
Imp. Schedule: FCR 83-24 i
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CCNPP Units 1 & 2 R.G.1.97, Revision 3
~
Item 40 of 63 Variable: Boric Acid Charging Flow (D-5)
Required Range: 0-110% design flow Category: 2 Existing Design: Boric acid charging flow is provided by three positive displacement charging pumps each with design capacity of 44 GPM.
Pump flow indication is provided via FI-212 on the main control boards. Indicator range is 0 - 150 gpm. Due to pressure pulsation from the positive displacement charging pumps, the flow indication is erroneous ( 15% of reading).
Evaluation: The instrumentation provided is not in accordance with the guidelines of R.G.1.97.
Position: In an on-going effort to remedy the erroneous flow readings, we have installed pulsation dampeners in instrument tubing, replaced the Unit I transmitter, and investigated alternate designs which l would remady the inaccuracies. Tne testing performed to date indicate significant improvement in performance, but the present accuracy of approximately i 15% is still unacceptable for post- l accident monitoring. We have currently installed strap-on !
ultrasonics to verify the transmitter error. Testing is in l progress and is scheduled to be complete in approximately three months. Test results will be used to determine acceptability of existing transmitter or used as a basis for design of a replacement unit in accordance with R.G.1.97 requirements .
l Imp. Schedule: FCR 85-1023 l
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CCNPP Units 1 & 2
', R.G.1.97, Revision 3
]
l Item 41 of 63 i i
i Variable: Neutron Flux (B-1) l Required Range: 10E-6% to 100% full power 1
Category: 1 i Existing Design: Four independent and redundant channels are provided. Each channel has a Wide Range (10E-8% to 150% full power) and a Power l Range (0.1% to 200% full power). l )
Two indicators per channel are provided on panel C05. One indict. tor is for the Wide Range and the other indicator is for j the Power Range. !
l Power for each loop is supplied from separate Class IE sources j ar d the electrical installation is in accordance with BG&E's i criteria for safety related circuits.
The harsh environment instruments are not qualified.
1 Evaluation: The system functionally meets the guidelines of R.G. 1.97. l However, the in-containment equipment is not gralified. l Position: A new four channel environmentally qualified wide range nuclear instrumentation configuration has been approved for installation.
All R.G. l.97 requirements will be satisfied when this installa-tion is complete.
Imp. Schedule: FCR 82-150 l
-. . r_ ,- .-.mg . , - , -,, . . - - ? p
, , CCNPP Unita 1 & 2 1 R.G. 1.97 Revision 3 Item 42 of 63 Variable: Control Rod Position (B-2)
Required Range: Full-in or not full-in Category: 3 Existing Design: Three separate Control Rod Position ind:cators are provided. The ptimary indicator is a digital rod position indicator (I rod per group) which displays rod position in increments of 3/4" from full-in to full-out via the plant computer. A bar graph display is provided on the metrascope for a!! CEAs from full-out to full-in in increments of 2". The third position indication utilized the reed switches to drive a mimic board with four multicolored indicator lights.
Evaluation: The instrumentation meets the reauirements of R.G. 1.97.
Position: No changes are necesst.ry.
Imp. Schedule: N/A i
)
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', CCNPP Units 1 & 2
- R.G.l.97, Revision 3 Item 43 of 63 Variable: Containment Pressure (A-10, B-13, B-15, C-5 and C-1 t)
Required Range: -5 psig . to three x design pressure n
Category; 1 Existing Design: Three instrument loops are provided to measure containn.ent pressure. Two loops cover the full range required from -5 psig I to 150 psig (design pressure is 50 psig)
All three channels are indicated on panel C09 and the -5 to 150 psig channels are also input to the TSC.
Power for the loops is supplied from '~'verter fed, battery backed-up Class IE power sources. The electrical installation is I in accordance with BG&E's criteria for safety related circuits. )
No part of loop is located in harsh environment.
l Evaluation: The instrumentation provided is adequate and is sufficient for l PAM. :
l Position: No further changes are necessary. l l
Imp. Schedule: FCR 83-101-Complete l l
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CCNPP b aits 1 & 2 i
'. R.G.1.97, Rcvision 3 i l
g Item 44 of 63 1
I Variable: Containment Atmosphere Temperature (D-24)
Required Range: 40 degrees F to 400 degrees F i
Cater,ory: 2 l Existing Design- One instrument loop which monitors from 50 degrees F to 300 degrees F. The instrument sensor is located in the containment dome.
Indication is provided on C10 with an indicator range of 50 degrees F - 300 degrees F. l Power for the loop is su .,slied from highly reliable instrumenta-i tion bus that is backedeup by a diese! generator. The electrical installation is in accoia .nce with BG&E's criteria for non-safety related circuits.
The harsh environment equipment is not "qualified" in accordance with the requirements of 10 CFR 50.49 as applicable.
- Evaluation
- The instrumentation does not meet the required span range of 40 1 degrees F - 400 degrees F. However, the maximum temperature i predicted during a postulated accident is 274 degrees F inside l l the containment. Therefore, the range of 50 degrees F - 300 degrees F is satisfactory for PAM.
l Position: The temperature elements will be replaced with environmentally )
l qualified elements. i i l Imp. Schedule: FCR 84-1086 l
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1 CCNPP Units I & 2 z'
+ R.G.1.97, Revision 3 Item 45 of 63
)
i Variable: Containment Hydrogen Concentration (C-10) j i
Required Range: 0 to 10% Volume Hydrogen Category: 1 1
Existing Design: Two redundant instrument loops are provided to measure -the % !
volume of hydrogen from 0 to 10%. l l
Indication is on C10 and is provided via an indicator / recorder. ;
i l
Power for each loop is supplied from separate Class lE buses that J are backed-up by diesels. The electrical installation is in .
accordance with BG&E's criteria for safety related circuits. I The harsh environment equipment is "qualified" in accordance with I the requirements of 10 CFR 50.49 as applicable. I 1
Evaluation: The instrumentation provided is adequate and sufficient for PAM. )
Position: No changes are necessary.
l Imp. Schedule: N/A <
1 I
-~ + -- , r. - _ . - , ,n _. ,,y4, --4 - , , - - , - . , 4,.---
7 -. ,
CCNPP Units I & 2 R.G.1.97, Revision 3 )
Item 46 of 63 Variable: Heat Removal by Containment Fan Heat Rem. System (D-23)
Required Range: Plant Specific Category: 2 Existing Design: Each fan has its own cooling water flow instrument loop which is used to remove heat.
Flow indicators are provided on C09 to monitor the flow over a range of 0-2500 gpm.
Power for each loop is supplied from highly reliable instrumentation buses that are backed-up by diesels. The electrical installation is in accordance with BG&E's criteria for non-safety related circuits.
The harsh environment equipment will be qualified in accordance l with the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation provided does not meet the guidelines of R.G. 1.97.
Position: The instrumentation will be upgraded to comply with 10 CFR 50.49.
Imp. Schedule: FCR 87-112 i
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CCNPP Units 1 & 2 y R.G. 1.97, Revision 3 1
Item 47 of 63 Variable: Containment Spray Flow (D-22)
Required Range: 0-110% Design Flow Category: 2 Existing Design: One instrument loop is provided for each Containment Spray header. The instrumentation spans a design flow of 0 to 148%
l Indication is prosided on C09 for one spray header and the other header has indication on C08. The indicator range is 0-2000 gpm and the de:ign flow is 1350 gpm.
Power for each loop is supplied from highly reliable instrumenta-tion buses that are backed-up by diesels. The electrical installation is in accordance with BG&E's criteria for non-safety related circuits.
The harsh environinent equipment is qualified in accordance with the requirements of 10 CFR 50.49.
Evaluation: The instrumentation provided does meet the guidelines of R.G. 1.97.
Pesition: No changes are necessary.
Imp. Schedule: N/A
i CCNPP Units 1 & 2 I
- R.G.1.97, Revision 3 Item 48 of 63 l l
Variabla.: Containment Isolation Valve Position (B-14) l Required Range: Closed-Open Category: - 1 Existing Design: All remotely operated containment isolation valves - have remote valve indication. Manual valves are procedurally controlled without remote indication.
The design bases for fluid penetrations w hich require- isolation after an incident are given in section 5.2.2 of the FSAR.
Penetrations which require redundant remotely operated valves have redundant indication for that penetration with a position indicator on each valve.
Position indication for remotely operated valves are designed and -i installed in accordance with the valve's requirad function and failure mode.
Position swit:hej on valves which have their normal, failed and functionally safety related position different from the other, or change position in the performance of its safety related function are installed in accordance with BG&E's criteria for safety related circuits, and are classified as safety-related. 5 1
j Power for in'!ication of valve position for all safety-related position switches is supplied from Class IE sources. These Class IE sources are either a 125 volt battery bus or an AC bus backed-up by a diesel. The electrical installation for ,
a safety-related position switches is in accordance with BG&E's l criteria for safety related circuits.
The harsh environment equipment for the safety related position switches is qualified in accordance with the requirements of 10 i 2 CFR 50.49 as applicable.
Evaluation: The instrumentation provided is adequate and sufficient for PAM. ;
Position: No further action is required.
l Imp. Schedule: FCR 85-1051 - Complete t
1 i
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l
', CCNPP Units 1 & 2 l R.G.1.97, Revision 3 Item 49 of 63 Variable: Component Cooling Water Temp. to ESF (D-29)
Required Range: 40 to 200 degrees F Category: 2 Existing Design: One instrumentaticn channel is provided for each of the component cooling heat exchanger outlet lines. These instruments cover a range of 50 degrees F to 200 degrees F, Indicators are provided on panel Cl3.
Power for each of the loops is supplied by highly reliable non-Class IE instrumentation buses that are backed-up by diesels.
The elNtrical in. Milation is in accordance with BG&E's criteria ,
for non-safety relateo circuits.
The et,uipment was not included in our EQ program.
Evaluation: While the range is slightly 1, ., than required, the instrynentation range provided is adequate and sufficient for a
PAM The EQ status of equipment do not meet R. G. 1.97 requirements.
Tasition: The temperature elements will be replaced with environmentally qualified elements.
8.np. Schedule: FCR 84-1086 1
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. , CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 50 of 63 Variable: Component Cooling Water Flow to ESF (D-30)
Required Range: 0 to 110% design flow Category: 2 Existing Design: CCNPP does not have any flow indicators for Component Cooling Water flow to the ESF system. Operators detarmine that adequate flow to the pumps is available by observing component coohng header pressure. The header pressure instrumentation, though safety-related is not qualified in accordance with _ the requirements of 10 CFR 50.49 as applicable. The header pressure range is sufficient to denote the entire range of component cooling pressures. The valves in the component cooling flow path are locked open and checked monthly.
, Evaluation: The existing instrumentation is sufficient for pal.4 conditions.
Position: The need to monitor CCW flow is considered not necessary. The component cooling header pressure instrumentation will be upgraded to meet the requirements of 10 CFR 50.49 as applicable.
4 Imp. Schedule: FCR 84-1088 E
' As i . ,
CCNPP Units 1 & 2
- R.G.1.97, Revision 3 Item 51 of 63 Variable: Emergency Yentilation Damper Position (D-33)
Rcquired Range: Open-Cic;,co Status Category: 2 Existing Design: Three ventilation systems provide filter ventilation in the Auxiliary Building. l The Penetration Rocm Exhaust Damper Indication is provided by indication on C09 of the damper positioning air solenoid valve energized /de-energized state and the fan motor run condition.
Damper position switches also provide input to the plan
- computer.
The ECCS Exhaust Damper Indication is provided by indicatlan on IC34 of the damper positioning air solenoid valve energized /de-i energized state and the fan motor run condition. ,
l The Spent Fuel Pool Exhaust Damper Indicatiori is provided by 1 indication on IC34 of the damper positioning air solenoid valve energized /de-energized state and the fan motor run condition.
Evaluation: The Penetration Room Exhaust Dampers are being replaced by gravity operated dampers. These dampers will open upon start of i the penetration room exhaust fans. Since no outside force or signal is needed to operate the dampers, no position indication I is deemed necessary. l l Position: Damper position indication will be added for the ECCS and Spent Fuel Pool Exhaust Dampers en C34. Position switches and cables located in harsh areas will comply wh the requirements of
!0 CFR 50.49. l 1
Imp. . 'hedule: FCR 84-1088 l '
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CCNFP Units 1 & 2
. ~. R.G.1.97, Revision 3 Item 52 of 63 Variable: Status of Standby Power, etc. (D-34)
Required Pange: Voltages, currents, pressures Category: 2 Existing Design: 4KV Class IE Systems:
Each of the 4, 4 KV Class IE buses have the following instrumentation available in the control room for monitoring purposes.
480V Bus Voltsge 4KV Bus Vo.' age 4KV Bus Potential Indicator 4KV Bus Current Individual 4KVload Ammeters 480V Bus Potential Indicator The 4KV Class IE systems have the following annuniciated in the control room:
4KV Bus Main Bkr, li'd Center Feeder Bkr, and DG Feeder Bkr Trip Alarm 4KV MotorOverload Alarm 480V Motor Overload /Under-voltage Alarm Diesel Generators Each of the 3 diesel generators have the following instrumenta-tion available in the control room for monitoring purposes:
Varmeter (2500-0-2500)
Wattmeter
{
(0-3500 KW) I Ammeter (0-600 A)
Voltmeter (0-5.25 KV)
Frequency Meter (58-62 liertz)
[ Each of the 3 diesel generators have the following alarms in the l control room:
Voltage or Frequency Abnorma!
Engine or Exciter Shutdown Generator Fault Trip 120 Volt Vital AC System 1
, - _ -a
CCNPP Units 1 & 2
~. R.G.1.97, Revision 3 Item 52 of 63 -
Each of- the 4-120V Vital AC Systems (per unit) have the following instrumentation available in the control room:
Inverter AC Voltmeter (0-150V)
Inverter AC Ground Indication Inverter Position Switch Indication Each of the 4-120V Vital AC Systems per unit have the following
, alarms:
Inverter AC Under-voltage Each of the 4-120 voit Vital AC Systems have the following local
~
instrumentation:
Inverter DC Input Voltmeter Inverter AC Output Voltmeter Inverter AC Output Ammeter Inverter AC Frequency Meter Each of the 4-120V Vital AC Systems have the following annunciating on the Plant Computer:
Inverter AC Ground Indication Inverter AC Uncier-voltage 125 Volt Vital DC System i All 4 Class IE 125 volt DC systems have the following instrumentation available in the control room for monitoiing purposes.
125 Volt DC Bus Voltage (0-150V) 125 Volt Battery Current (1000-0-1000A) ,
f 25 Volt Bus Ground Indication Battery Charger Current (0-500A)
Battery Breaker Open Indication 125 Volt DC Panel Potential Indication The 125 Volt DC Systems have the following ularms in the Control Room:
Battely Breaxei Open Alarm 125 Volt DC Bus Under-voltage Alarm
j i
CCNPP Units 1 & 2 R.G.1.97, Revision 3 l I
Item 52 of 63 The 125 Volt DC Systems have the following local instrumentation:
125 Volt DC Bus Under-voltage 125 Volt Battery Current 125 Volt DC Bus Ground Indication Battery -Charger Current Battery Charger Voltage The 125 Volt DC Systems have the following alarm points also annunciating on the Plant Computer:
125 Volt DC Bus Under-voltage Charger AC Under-voltage Charger DC Under-voltage The electrical installation of all instrumentation associated with the 125 Volt DC Class IE System and the 120 Volt AC Class IE System is in accordance with BG&F.'s criteria for safety related circuits.
The electrical installation of the 4KV Class IE System is in accordance with BG&E's criteria for non-safety related circuits (with the exceptior. of individual 4KV load ammetars and Diesel Generator 12 instrumentation).
Evaluation: The instrumentation provided is adequate and sufficient for PAM.
Position: The cables for instrumentation associated with Diesel Generators 11 and 21 have been upgraded. l The cables for instrumentation associated with the 4KV & 480V {
Class IE buses have been upgraded.
Imp. Schedule: FCR 84-1091 and FCR 84-1092 l
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.9 CCNPP Units 1 & 2
- R.G.1.97, Revision 3 Item 53 of 63 '
Variable: Primary Coolant Rad Monitor (C-2)
Required Range: 1/2 Tech. Spec. limit to 100 times Tech. Spec. limit
- Category
- 1 Existing Design; One instrument loop is provided to measure activity over a range of 0 to 10 CPM. One indicator / recorder is provided on panel C07.
Evaluation: The Tech. Sptc, limits are ! ,uCi/ gram Dose Equivalent I-131 and 100/E A Ci/ gram. Grab samples are taken and analyzed to verify Tech. Spec. activity limits. The instrument loop is not used for Tech. Spec. compliance. In addition, this process radiation instrument loop is isolated in the event of Safet) Injection Actuation via the RCS Letdown Isolation Control Valves. This instrument loop is only used during operation and for gross activity changes. PAM is accomplished by accident sampling analysis (Item 63).
Power for each loop is supplied by highly reliable non-Class IE I instrumentation buses that are backed-up by diesel generators.
The electrical installation is in accordance with BG&E's criteria for non-safety related circuits.
Position: A downgrade to Category 3 indication requirements is appropriate. !
No changes are necessary. l Imp. Schedule: N/A l
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. l CCNPP Units I & 2 R.G.1.97, Revision i stem 54 of 63 Variable: Primary Coolant Gamma Spectrum (C-3)
Required Range: Isotopic Analysis !
Category: 3 ,
Existing Design: Diluted grab samples can be taken and analyzed in the lab facilities.
Evaluation: The instrumentation meets the stated guidelines of R.G. 1.97.
Position: No changes are necessary.
Imp. Schedule: N/A B
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CCNPP Units 1 & 2
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- R.G.1.97, Revisic n 3 Item 55 of 63 Variable: Containment Area Radiation - liigh Range (C-7 & E-1)
Required Range: 1 to 10E+7 R/Hr
]
Category: 1 Existing Design: Two separate channels of High Range Containment Area Radiation are provided. The displayed range is I to 10E+8 R/lir with an energy response from 0.1 to 3 MeV. The indicators are located in the Main Control Room on panel 2C24D with high level annunciation on the snain annunciator system.
Power for each loop is supplied from separate inverter fed, battery backed up Class IE sources. The electrical installation is in accordance with BG&E's criteria for safety related circuits.
The harsh environment equipment is qualifiable in acecrdance with the requirements of 10 CFR 50.49 as applicable.
Evaluation: The instrumentation provided is adeouste and sufficient for the intended monitoring function.
Position: No changes are necessary.
Imp. Schedule: N/A 4
i a
a
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CCNPP Units 1 & 2
- R.G.1.97, Revision 3 ;
i Item 55 of 63 Variable: Containment Purge Effluent Radioactivity. Auxiliary Building Effluent Radioactivity, Condenser Air Removal System Exhaust Radioactivity and All Other Identified Effluent Points Radioactivity (C-8, C-12, C-13, E-3, E-4, E-5 E-6, and E-9)
Required Range: Various from 10E-6 to 10E+2 AiCi/cc and from 10E-6 to 10E+54:Ci/cc Category: 2 Existing Design: Airborne process radiation monitors exist for monitoring condenser vacuum pump discharge radiation and ventilation exhaust radiation - for certain rooms in the Auxiliary Building. Ilowever, in accordance with R.G.1.97, Rev. 3 these monitors are not needed for PAM due to the fact that the effluents discharge through the common plant vent. (See variable sheet later for common plant vent monitor).
i Individual radiation monitors are not needed since effluents Evaluation:
exhaust to a common plant vent that is monitored.
Position: No changes are necessary.
Imp. Schedule: N/A ,
t 4 i 8
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'. CCNPP Units 1 & 2 R.G.1.97. Revision 3 Item 57 of 63 Variable: Common Plant Vent - Noble Gu and Vent Flow Rate (E-7)
Required Range: 10E-6 AaCi/cc to 10 E+3 AaCi/cc Category: 2 Existing Design: liigh range, midrange and low range detectors monitor Main Vent Noble Gas activity in a range from 10E-7 to 10E+5 AaCi/cc.
Indication is provided for activity and flow on panel 2C24B and activity is recorded on trend recorders on 2C26.
Each loop is powered from Class IE diesel backed motor control centers. The electrical installation is in accordance with BG&E's criteria for safety-related circuits.
No equipment is exposed to a harsh environment.
Evaluation: This instramentation is adequate and sufficient for the intended monitoring function.
Position: No changes are necessary.
Imp. '&hedule: FCR 33-1077 (Complete)
FCR 83-1078 (Complete)
^
CCNPP Units 1 & 2 R.G.1.97, Revision 3 l
f item 58 of 63 Variable: Area Radiation (E-2)
Required Range: 0.1 to 10E+4 R/Hr Category: 3 Existing Design: The Area Radiation Monitoring System reads out and records beta-gamma radiation levels in selected areas throughout the plant and alarmt (audible and visual) if these levels exceed a preset value or if a detector fails. Indi:ators with a range of -
- 0.1 mR/hr to 10R/hr are located on Main Control Room panel IC22, i
Evaluation: The range is not within the recommendation of R.G.1.97. l The intended function of the Area Radiation Monitoring System is Position:
personnel protection and the present range is sufficient for that -
purpose. The functions of detection of releases, release '
assessment and surveillance are performed through Health Physics procedures with supplemental information provided oy the effluent monitors. Therefore, no changes are necessary.
l Imp. Schedule: N/A I
l 1
l l
I 1
l i
l 5 I I
l
'. CCNPP Units 1 & 2 l . .
R.G.1.97. Revision 3 ,
Item 59 of 63 Yariable: Radiation Monitoring for the Vent from Steam Generator Safety Relief Valves and Atmospheric Dump Valves (E-8) i Required Range: 0.14:Ci/cc to 10E+3 #Ci/cc mass of steam released (E-8)
Category: 2 i l Existing Design: One detector located adjacent to each steam line upstream from l the Relief Valves and Dump Valves monitor steam line activity, i The detectors are located in lesd shields to prevent interference from background radiation. l Indication with a range of IR/hr to 10E+7 R/hr is provided on Main Control Room panel 2C24B. Correlation curves will allow !
conversion of the indicator readings in R/hr to 42Ci/cc. I
~ Power is supplied from inverter fed, battery backed-up Chss IE l ,
sources and tht- electrical installation in accordance with BG&E's !
criteria for safety related circuits. l The instrumentation is not environmentally qualified for post accident conditions and was not included in the EQ Program, l
Evaluation: Since the only postulated event requiring this equipment is a l Steam Generator tube rupture, the instrumentation does not l l require qualification for steam 1:ne break or LOCA. The <
l Instrumentation is adequate and is suf ficient for PAM.
l l No changes are necessary.
Position:
J Imp. Schedule: N/A l
1 l
l l 1
i I
. CCNPP Units 1 & 2 R.G.1.97, Revision 3 i
item 60 of 63 i Variable: All identified plant release points (E-10)
Required Range: 0.001 AiCi/cc to 100.uCi/cc Category: 3 l Existing Design: Instrumentation is provided to monitor Msin Vent effluent for ,
radioactive particulates and halogens. The range is 10E-Il 4:Ci/cc to 5 x 10E-7 AsCi/cc for particulates. Halogens are sampled and analyzed off-line.
Indication is provided on Main Control Room panel C22 and high radiation is alarmed on the annunciator system. >
i Power is supplied from highly reliable non-Class IE instrumenta- ,
l tion buses that are backed-up by diesels. The electrical installation is in accordance with BG&E's criteria for non-safety related circuits.
Evaluation- The range does not meet the guidelines of R.G. l.97. However, it j is sufficient for the purpose of monitoring plant releases.
A wide range noble gas monitor continuously monitors noble gas in ;
the main plant vent, in addition, it is equipped for particulate i and iodine grab samples. Based on a correlatian between noble gas and iodine concentrations a rough indication of lodine levels t can be obtained from the noble gas monitor. In the event that l noble gas concentrations are high, grab samples can be taken at time intervals necessary to achieve the higher range recommended i by R.G.1.97 for iodine and particulates.
Position: No changes are necessary.
t Imp. Schedule: N/A !
I i
i I
j I
1 l
l l
. CCNPP Units 1 & 2
- R G.1,97, Revision 3 l Item 61 of 63 Variable: Environ Radiation and Radioactivity (E-II, E-12, and E-13)
Required Range: Various Category: 3 Existing Design: Portable instrumentation and on-site instrumentation exist at l CCNPP to measure and analyze samples to meet the general intent l of R.G. 1.97. l Evaluation: The equipment and facilities are adequate and sufficient for PAM, l Position: No changes are necessary.
Imp. Schedule: N/A l
1
[
j !
4 e
i 1
l l
4 l
1 l
i
)
. I l
CCNPP Units 1 & 2 l
i R G.1.97, Revision 3 l Item 62a of 63 Variable: Wind Direction (E-14)
Required Range: 0 to 360 degrees i 5 degrees t l Category: 3 !
( Existing Design- Instrumentation is provided to measure wind direction on the l
meteorological tower at the 60 meter and 10 meter elevations.
The range is 0 degrees to 360 degrees i 3.6 degrees with a I ,
starting threshold of 0.33 meters per second. Indica: ion is l
prov'. ' on Main Control Room panel IC22G. !
Evaluation: The instrumentation provided is adequate and sufficient for the intended monitoring function.
Position: No changes are necessary.
Imp. Schedule: N/A r r
I l
1 i
l l
l 1
l l
i l
I l
l i
I l
1 L-_ _ _- ___ __ _ _ _ _ - _ -1
i 1
CCNPF Units 1 & 2 i R.G. l.97, Revision 3 Item 62b of 63 lI i
Variable: Wind Speed (E-15) { ;
Required Range: 0 to 22 meters per second 10.2 mps with starting threshold of ;
less than 0.4 mps.
] Category: 3 l l
Existing Design: Instrumentation exists to measure wind speed on the meteorologi- ,
cal tower at the 60 meter and 10 meter elevations. The range is l 0 to 50 :neters per second 0.11 meters per second with a ;
starting threshold of 0.33 meters per second. Indication is provided on Main Control Room panel IC220. !
Evaluation: The instrumer.tation provided is adequate and sufficient for the i intended monitoring function.
No changes are necessary. !
Position:
- Imp. Schedule
- N/A !
T i t' 0
~
i i
i I
4 I
I i
i I
.i I
l I
1
.. -- . . . . . . _ _ . - . .. . ~
. . CCNPP Units 1 & 2 'I
- R.G. l.97, Revision 3 '
Item 62c of 63 f
Variable: Estimation of Atmospheric Stability (E-16) ;
, Required Range: -5 degrees C to 10 degrees C i 0.15 degrees C per 50 meter intervals.
Category: 3 )
Existing Design: Instrumentation is provided to measure atmospheric stability on the meteorological tower. Sensors mounted at 60 meters and 10 l e meters have a range of -30 degrees C to 50 degrees C.
Temperatures difference are displayed in the Main Control Room on panel IC22G with a range of -3 degrees C to 7 degrees C i 0.16 degrees C.
1 Evaluation: The range does not meet the recommendations of R.G. I o' but the i instrumentation is adequate for the intended monitoring function. l i Position: No changes are necessary. 1 Imp. Schedule: N/A I
l l
1 l
I 4
i 1
.. a .- - - -
CCNPP Units 1 & 2
. . R.G. l.97. Revision 3 I Item 63a of 63 Variable: Primary Coolant and Sump - Gross Activity (E-17) l Required Range: ; AiCi/mt to 10 Ci/mi Category: 3 Existing Design: Diluted grab samples can be taken and analy r;;d in the lab facilities.
Eva'ntion: Meets the guidelines of R.G.1.97.
Position: No changs are required.
Imp. Schedule: N/A i
1
t CCNPP Units 1 & 2 i
. . R G. l.97, Revision 3 L
1 Item 63b of 63 :
l Variable: Primary Coolant and sur.4 - Boron Content (E-17) i t
. Required Range: 0-6000 ppm I
Category: 3 Existing Design: A diluted grab sample can be analyzed in the chemistry lab for :
Boron Concentration that meets the requirement range of 0-6000 i ppm.
Evaluation: Meets the guidelines of R G.1.97 .
- Position
- No changes are necessary i imp. Schedule: N/A t
i j i i
i a
J t
.. i h
I t
j F
P P
4 4
i e
4
! i
6 .
CCNPP Units 1 & 2
. . R.G.1.97. Revision 3 Item 63c of 63 Variable: Primary Coolant and Sump - Chlorine Content (E-17)
Required Range: 0-20 ppm Category: 3 Existing Design: A diluted grab sample can be obtained for analysis in the chemistry lab.
Evaluation: Meets the guidelines of R.G. l.97. l Position: No clianges are necessary.
Imp. Schedule: N/A I
l l
I l
i
9
. , CCNPP Units 1 & 2 l
. . R.G. l.97, Revision 3 l Item 63d of 63 1
Variable: Primary Coolant and Sump - Dissolved liydrogen (E-17)
Required Range: 0-2000 cc/Kg P
Category: 3 Existing Design: A- total gas sample can be obtained for analysis in the chemistry lab.
u ,
- Evaluation
- Meets the guidelines of R.G,1.97.
Position: No changes are necessary Imp. Schedule: N/A ,
l t
i l
l l
J l i
i I
1 l !
i
}
l a
=-e + -, p&e ..-,----r m--- ,e-_-,--- < --., ,,
_ _ _- - .- .. .=. ... - -
9
. CCNPP Units i a 2 !
. R.G. l.97 Revision 3 l item 63e of 63 r
Variable: Primary Coolans cnd Sump - Dissolved Oxygen (E-17)
Required Range: 0 - 20 ppm l I
Category: 3
]
l Existing Design: As part of the review of the Post Acc! dent Sampling System i
,. (PASS), BG&E in an April 1,1986 letter from J. A. Tiernan to A. C. Thadani, stated that dissolved oxygen monitoring is not required. The NRC in a May 6,1986 letter from D. H. Jaffe to ,
J. A. Tierr.an approved PASS as piesently configured and stated j that measuring oxygen concentration is not mandatory.
No instrumentatica is required. I Evaluation: I Position: No changes are riccessary imp. Schedule: N/A I
k I .
- i A
t i
J l
i l i
l l
l ;
-l 2
4 Y
4
)
! I b l 1
i ,
).
m 1
- CCNPP Units 1 & 2 R.G.1.97, Revision 3 item 63f of 63 l Variable: Primary Coolant and Sump - pli (E-17)
Required Range: I to 13 Category: 3 -
Existing Design: As part of the review of Calvert Cliffs' PASS, NRC in a May 6,1986 letter from D. H. Jaffe to J. A. Tiernan, agreed with BG&E's position that pH monitoring was r:ot required for PASS. ,
Evaluation: No instrumentation is required.
Position: - No changes are necessary.
Imp. Schedule: N/.\
e i
i F
i l
1 s !
l 4
)
1
i CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 63g of 63 Variable: Containment Air - liydrogen content (E-18)
Required Range: 0-10 % Volu ne Category: 3 Existing Design: Reference Item 45 (Containment Atmosphere flydrogen Concentration)
Evaluation: Same equipment at for Item 45. Meets requirements of R.G. 1.W for Category I equipment.
Position: No changes are necessary imp. Schedule: N/A
1 er
- CCNPP Units 1 & 2 R.G.1.97, Revision 3 Item 63h of 63 Variable
- Containment Air - Oxygen Content (E .88)
- Gamma Spectrum Required Range: 0-30 %
Category: 3 Existing Design: A grab sample can be obtained and analyzed in the chemistry lab.
Evaluation: Meets the guidelines of R.G.1.97. l Position: No changes are necessary Imp. Schedule: N/A
'l 1
i e
i k
4 r
i l
1 ym--<-.- . -
y-,. -
l
+ . l l
l ATTAClih1ENT C R.G. 1.97 INPUT SUbih1ARY BALTIh10RE GAS AND ELECTRIC COh1PANY AUGUST 1988
9 e
i ATTACliMENT C R.G.1.97 INPUT
SUMMARY
ITEM VARIABLE CAT DAS SPDS TSC EOF 1 Pressurizer Level I
- 5 * *
- 2 Pressurizer Pressure 1 Pressurizer Temperature 3 3
4 Pressurizer 3 pray Temp 3 5 Pressurizer IIeater Status 2 6 2
- PRV Position / Flow 7 Steam Generator Level 1 *5 * 'S *$
8 Steam Generator Pressure I * * *
- 9 Steam Generator Steam Flow 3
- CVCS Make Up Boric Acid 3 18 19 CVCS Letdown 3 20 RWT Level 2 Condensate Storage Tank Level * *
- 21 1 22 Containment Sump Level - NR 3 Containment Sump Level - WR I * * *1 23 'l 24 Containment Sump Water Temp ----------
NOT REQUIRED --------
25 111 Radiation Liq. Tank Level 3 26 Radiation Gas Tank Pressure 3 RCS Temperature (IiOT) *S * '5 '5 27 1 RCS Temperature (COLD) *5 * *S '5 28 1 Subcooled Margin I * * *
- 29 Reactor Level Monitoring '6
- I 30 1 Core Exit Thermocouples * * *
- * '4 '4 1 33 RCP Status 3 34 Main Feedwater Flow 3 35 Auxiliary Feedwater Flow 2 36 IIPSI Flow 2 37 LPSI Flow 2 38 Decay IIeat Removal Flow 2 39 Decay liest Removal Temperature 2 Doric Acid Charging Flow 2 * * *
- 40
- * *l,3 41 Neutron Flux I
- l .3
- I 42 CEA Position 3 43 Containment Pressure I 44 Containment Temperature 2 '5 *
- 1 *1 W
,' ATTACIINTENT C R.G.1.97 INPUT SUhthi ARY ITEhi VARIADLE CAT DAS SPDS TSC EOF 45 Containment liydrogen Concentration 1
- * *2 *2 46 Containment liest Removal 2 47 Containment Spray Flow 2 * * *
- 48 Containment isolation Valve Position 1 49 Comp Cooling Water to ESF 2 (Temperature) 50 Con'p Cooling Water Flow to ESF 2 51 Emergency Vent Damper Pos. 2 *
- 52 Status of Standby Power 2 *
- * *1 55 Containment Area Radiation 1 'l Condenser Offgas Radiation *
- 56 N/A 'l *1 l
- * *1 57 hiain Vent Radiation / Flow 2 'l 58 Area Radiation 3 *
- Rad hionitor hiain Steam Safety *
- 59 2 l RVs & Atmospheric Dump Valves 60 Airborne Radiation 3 g
61 Plant & Environment Radiation 3 hieteorology * *1 *1 62 3 63 Accident Sample Analysis 3 Note 1: Scheduled to be added with FCR 83-1029 & 82-1000 Note 2: Only the Cntmt Dome Sample is hionitored Note 3: Only Thermal Power is currently given Note 4: RCP status is given by RCS Flow Note 5: Same parameter is being measured but not by the same instrument loop as evaluated in R.G.1.97 Note 6: Scheduled to be added with FCR 80-1010