ML17321A467
| ML17321A467 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/28/1985 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17321A466 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8503050268 | |
| Download: ML17321A467 (30) | |
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ENCLOSURE TO AEP:NRC:0773J STATUS REPORT IMPLEMENTATION PLAN OF REGULATORY GUIDE 1.97, REVISION 3, FOR THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 8503050268 850228 PDR ADOCK 050003i5 l F PDR
TABLE OF CONTENTS I. Background II. Status Report III. Tables IV. Footnotes
AEPSC hired, in August 1984, the engineering consulting firm of DiBenedetto, Farwell & Hendricks in order to perform the detailed design study required to determine the Donald C. Cook Nuclear Plant (DCCNP) Units 1
& 2 compliance with Regulatory Guide 1.97, Revision 3. A final report on this subject is expected by June, 1985. This document presents preliminary findings that have resulted from our discussions with the consultant. This report may be modified at the time we receive the final report, and for that reason we are expecting to update this status report later this year.
The dates for modifications contained in this report are currently scheduled target dates. It must be recognized however, that equipment delivery delays, test difficulties, or other problems may cause delays in this schedule.
Certain requirements of Regulatory Guide 1.97 were judged to be unreasonable to backfit in an operating plant. Justification is provided for these requirements to which. we take exception.
The table included with this enclosure contains information regarding instrument range, environmental qualification, seismic qualification, quality assurance, redundancy, power supply, location of display and required actions and schedule for each type A,B,C,D, and E variable listed in Regulatory Guide 1.97, Revision 3. This table is consistent in organization with Table 3 (PWR Variables) of Regulatory Guide 1.97, Rev. 3 dated May, 1983. In some instances, the .Type B-E variables are duplicated by the Type A variable listing. In these instances, reference back to the Type A variable is made because the requirements for Type A variables are the most stringent. The schedule and status for each instrument indicates when the requirements of Regulatory Guide 1.97 as described in this enclosure will be met. Open items are indicated by TBD (To Be Determined). Deviations from the Regulatory Guide and justification for the deviations are given in the footnotes located at the end of this enclosure. The following general notes provide clarifications for each category of information requested by section 6.2 of Supplement 1 to NUREG 0737 with the exception of instrument range, which is self explanatory:
- 1. Sensor Location The "sensor(s) location(s)".information requested in Section 6.2(e) of Supplement 1 to NUREG 0737 is assumed to mean the application and not physical plant location. This information i's provided in the column labeled "variable."
- 2. Environmental uglification Instruments reported as environmentally qualified (marked "yes" in the column labeled "EQ") are planned to meet the provisions of 10 CFR 50.49. As allowed by 10CFR 50.49(k),
original DCCNP instrumentation located in a potentially harsh environment has been qualified in accordance with the "DOR Guidelines". Equipment ordered after February 22, 1983, is to have environmental qualification in accordance with Category I of NUREG 0588 (For Comment) (i.e. IEEE Std 323-1974) unless there are sound reasons to the contrary. Consistent with 10CFR 50.49, DCCNP is not required to environmentally qualify equipment located in a mild environment.
- 3. Seismic uglification Instruments reported as seismically qualified (i.e., marked "yes" in the column labeled "SQ") are planned to meet the provisions of the DCCNP Updated FSAR p. 7.2-12 (i.e.,
protection grade equipment is designed such that for a design basis earthquake, the equipment will not lose its capability to perform its design objective; namely, shut the plant down and/or maintain the unit in a safe shutdown condition.)
Typical equipment of this type originally installed at DCCNP was seismically tested by Westinghouse Electric Corporation as documented in WCAP-7397-L, "Topical Report Seismic Testing of Electrical and Control Equipment". No industry standards regarding seismic qualification existed at that time.
Equipment ordered for Regulatory Guide 1.97 upgrading is planned for seismic qualification in accordance with Regulatory Guide 1.100 (i.e., IEEE Std. 344-1975) unless there are sound reasons to the contrary.
- 4. ualit Assurance Instruments reported as meeting quality assurance requirements (i.e., marked "yes" in the column labeled "QA") are planned to meet the provisions of the DCCNP QA program as described in DCCNP Updated FSAR Section 1.7. This program, as described, satisfies the requirements of 10CFR 50, Appendix B.
The implementation of specific Regulatory Guides and ANSI standards regarding quality assurance are consistent with the commitments of DCCNP FSAR Section 1.7 Appendix A.
Instruments reported as meeting the single failure criterion or redundancy requirements (i.e., marked "yes" in the column labeled "SF") are planned for a minimum of two (2) redundant, electrically independent channels up to and including any isolation device. The display may be a common multi-pen recorder or a dual indicator. The redundant channels are also physically separated in accordance with the DCCNP Updated FSAR
- p. 7.2-4. Physical separation requirements for redundant Post Accident Monitoring Instrumentation channels will be established in a manner consistent with the application of separation criteria to existing plant IE instrumentation 6 control circuits. The extent of conformance to Regulatory Guide 1.75 for D. C. Cook Plant IE systems was given in the answer to question 40.6 in FSAR Appendix Q, Unit 2 p.40.6-2.
In some instances, redundancy will be provided by measurement of a diverse"variable.
Instruments reported as meeting Class IE power supply requirements (i.e., marked "IE" in the column labeled "PS")
are planned to be powered from IE power supplies such as the 120V AC instrument buses or the 250 V DC buses as described in the DCCNP Updated FSAR Sections 8.1 and 8.3.
- 7. Dis la Location The display will be indicated either inside the control room or at another location as permitted by Regulatory Guide 1.97.
- 8. Schedule The implementation schedule provided for each variable is the current best estimate of the completion of the final configuration for the associated instrument including
redundancy, final displays, power supplies, documentation of qualification and turnover to plant operations. The schedules are based on anticipated delivery and plant outage schedules.
Equipment delivery delays, environmental qualification test difficulties, or other problems, however, may cause delays in these schedules beyond our reasonable control. Since the Consultant's engineering study has not yet been completed and a final report has not been issued, some items listed may require revision or deletion. In some instances equipment may be added to the list. The final configuration will not be determined until the EOP's and DCRDR program have been implemented and integrated with the Regulatory Guide 1.97 schedule. Considering these factors, our overall target date for completion of work undertaken in r'esponse to Regulatory Guide 1.97 is December, 1991.
Most variables presently listed are measured with fully operational instruments, however, the instruments are not considered complete for the purposes of this enclosure until they meet Regulatory Guide 1.97 requirements as described in this enclosure. Note that instruments previously reported to the staff as meeting the requirements of NUREG 0737 or IE Bulletin 79-01B do not, in all cases, meet all of the requirements of Regulatory Guide 1.97.
The schedules provided in this enclosure for meeting Regulatory Guide 1.97 requirements are not intended to change any previous commitment regarding NUREG 0737 or 10CFR 50.49, whose requirements may be different.
II I. - TABLES These tables represent the status of the Donald C. Cook Nuclear Plant when 'e have completed all of the requirements associated with Regulatory Guide 1.97, Rev. 3.
it It does not, nor is intended to reflect the status of the plant as of the date of this letter.
Type A Variables: "those variables to be monitored that provide the primary information required to permit the control room operator to take specific manually controlled actions for which no automatic control is'rovided and that are required for safety systems to accomplish their safety functions for design basis accident events. Primary information is information that is essential for the direct accomplishment of the specified safety funtions; it does not include those variables that are associated with contingency actions that may also be identified in written procedures." Note: These variables are plant-specific and based on review of the D. C.
Cook Nuclear Plant Emergency Operating Procedures (EOP's) plus anticipated future changes to the EOP's. The schedule and status for each instrument indicated is for when all of the requirements of Regulatory Guide 1.97, Rev 3 will be met.
Item Purpose Variable Tag No.s Range E S Q S P Display Remarks/Action Req'd U-1 U-2 No. A F S Location Schedule Schedule A-1 Maintain Prcssur- Centrifigal IFI-51,52, 0-200 GPM Y Y Y Y IE Control Room Replace, control room 1987 re- 1987 re-izer Level during Chg Pump Flow 53,54 Panel SIS indicators with seismic fueling fueling S/G Tube rupture qualified equipment outage outage A-2 Manual Trip of RC RCS Pressure NPS-121,122 0-3000psig Y Y Y Y IE Control Room Replace control room 1987 re- 1987 re-Pumps based on RCS (wide range) Panel RHR recorder with seismic fueling fueling pressure qualified equipment outage outage A-3 NOT USFD A-4 See footnote (n) RCS Hot Leg NTR-110,120,32-700'F Y Y Y Y IE Control Room Replace recorders 1987 re- 1987 re-Temperature 130,140 Panel DTU with seismic quali- fueling fueling fied equipment outage outage A-5 Set makeup for RCS Soluble NSX-101,103 NA NA NA NA NA NA NA See footnote (a) NA NA automatic control Boron Concen-tration.
A-6 See footnote (n) RCS Cold Leg NTR-210>220> 32-700 F Y Y Y Y IE Control Room Replace recorders 1987 re- 1987 re-Temperature 230,240 Panel DTU with seismic quali- fueling fueling fied equipment outage outage
Item Purpose Variable Tag No.s Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. A F S Location Schedule Schedule A-7 Determination of S/G Prcssure MPP-210,211, 0-1200psig Y Y Y Y IE Control Room Replace control room 1987 re- 1987 re-required core exit 212,220, Panel SG indicators with seismic fueling fueling temperature by S/G 221,222, qualfied equipment outage outage Prcssure (ruptured) 230,231, 232,240, 241,242 A-8 Determination of Containment NLA-310 589.5 to Y Y Y Y 1E Control Room Replace control room 1987 re- 1987 re-adverse containment Sump Level NLI-311,320, 614 ft. el- Panel RHR indicators with seismic fueling fueling 321 evation qualified equipment outage outage (bottom uf sump to max flood level)
A-9 Manual Reduction of S/G Level BLP-110,111,29-137" wc Y Y Y Y IE Control Room Replace control room 1987 re- 1987 re-ECCS Flow Narrrow range 112%120, Panel SG indicators and/or fueling fueling 121,122, recorders with seismic outage outage 130,131, qualified equipment 132,140, 141,142 A-10 Manual Reduction of Pressurizer NLP-151,152, 0-1002 Y Y Y Y IE Control Room Replace control room 1987 rc- 1987 re-ECCS Flow Level 153 (essent- Panel PZR indicators and/or fueling fueling ially top (NLP-151 also recorders with seis- outage outage to bottom HSD) mically qualified not includ- equipment ing rounded portions)
A-11 See footnote (n) Primary System QR-107 A,B, NA Y Y Y NA IE Control Room See footnote (b) NA NA
'afety Relief C,D Panel RC Valve Position
Item Purpose Variable Tag No.s Range E 8 Q S P Display Remarks/Action Req'd U-l U-2 No. Q Q A F S Location Schedule Schedule A-12 Determination of Containment VRA- 1 310 > I R/ljtR to Y NA Y Y IE Control Room See footnote (c) NA adverse containment Area Radiation 1410, IX10 R/1lR Panel RMS Monitor Nigh (Unit I)
Range 2310, 2410 (Uni.t 2)
A-13 Manually establish Lower Contain-, PPP-300,311, -5 to +l2 Y Y Y Y IE Control Room Replace transmitters, 1987 re- 1987 re-or trip containment ment Pressure 302,303 psig Panel SPY indicators with qualified fueling fueling spray equipment outage outage A-14 Manually establish Upper Contain- PPA-310,3ll> -5 to 36psig Y Y Y Y IE Control Room Replace transmitters, 1987 re- 1987 rc-or trip containment ment Pressure 312,313 Panel SPY indicators, recorders, fucling fueling spray with qualified equipment outage 'outage A-15 Manual Reduction of Auxilliary FFI-210,220, 0-250 KPPN Y Y Y Y IE Control Room Redundancy provided by 1987 re- 1987 re-ECCS Flow Fccdwater Flow 230,240 Panel SC diverse variable S/C fueling fueling narrow range level which outage outage is qualified. Replace indicators with seismic qualified equipment A-16 Manual Transfer to RWST Level ILS-950,951 essentially NA Y Y Y IF. Control Room Replace indicators, 1987 re- 1987 re-cold leg recircula- Top to Panel SPY recorders with seismic fueling fueling tion in low level Bottom qualified equipment. Also outage outage in RWST see footnote (d)
A-17 Manual Trip or re- Degrees Sub- NA 0-199'F sub- Y NA Y NA IE Control Room See footnotes (b) and (c) NA NA duction of Press- cooling cooling Panel BA which apply beyond the urizer Spray and 0-199'F isolating devices ECCS Flow Superheat A-I8 Control Makeup Flow Make up FInw- QFI-200 0-200 CPM NA Y Y Y IE Control Room Replace control room 1988 re- 1989 re-During S/C Tube in Panel BA and indicators with seismic fueling fueling Rupture HSD qualified equipment outage outage (QFI-200). Add second redundant qualified channel
Item Purpose Variable Tag No.s Range E S Q S P Display Remarks/Action Req'd U-I 11-2 No. Q Q A F S Location Schedule Schedule A-19 Control Letdown Letdown flow- QFI-301 0-200GPH NA Y Y Y IF. Control Room Replace control room 1988 rc- 1989 re-Flow during S/C out Panel BA and indicators with seismic fueling fueling Tube Rupture HSD qualified equipment outage outage (QFI-301). Add second redundant qualified channel A-20 Hanual Control of RCP Seal In- QFA-210,220. 0-15 GPH Y Y Y Y IE Control Room Replace transmitters with 1990. rc- 1989 re-Seal injection flow jeccion Flow 230,240 Panel RCP qualified equipment. Add fueling fueling to establish redundant, qualified outage outage minimum charging channels. Replace flow exiscing control room Indicators with seismic qualified equipment A-21 See footnote (n) RHR Flow IF1-310,311, 0-8000 GPH Y Y Y Y IE Control Room Replace control room 1987 re- 1987 re-320,321, Panel RHR indicators with seismic fueling fueling qualified equipment outage outage A-22 See footnote (n) Lower Contain- NA NA NA NA NA Nh NA NA See footnote (c) NA ment'pray Flow A-23 See footnote (n) Intermediate N-35, Nh Nh Nh NA NA NA NA Sce footnote (f) NA Range Flux N-36 A-24 See footnote (n) Reactor Cool- NLI-110,111, Essentially Y Y Y Y IF. Control Room None required N* NA ant Inventory 120,121, Top to Hot- Panel SIS 130,131 tom of Ves-sel A-25 Manual Reduction of ECCS Flow Core T/C's Exit 141,142 T/C 1-65 200-2300 .F Y Y Y Y IF. Control Panel FI Room All required cables, connectors, indicators, signal processing equipment to be replaced with qualified equipment See foot-note (g)
See foot-note (g) t
Item Purpose Variable Tag No.s Range E S Q S P Display Remarks/Action Req'd U-I U-2 No. A F S Location Schedule Schedule A-26 Determining Status RCP Pump Ql,Q2,Q3,Q4 0-1200A NA TBD Y Y IE Control Room See footnotes (d), (k), TBD TBD of RCP during DBE Status Panel RCP & (m) and allow for manual trip if necessary A-27 See footnote (n) Pressurizer Croup AI,A2, ON/OFF NA TBD Y Y IE Control Room See footnotes (d) & (k) TBD TBD Neater Status A3,CI,C2,C3 Panel PZR A-28 Manual trip of CCP Breaker Pump IE,IW OPEN/CLOSE NA TBD Y Y IE Control Room See footnotes (d) & (k) TBD TBD RCP's Status Panel BA A-29 Manual trip of SI Pump Pump IN,1S OPFN/CI.OSE NA TBD Y Y IE Control Room See footnotes (d), (k), TBD TBD RCP's Breaker Status Panel SIS & (m)
A-30 Manual trip of RCP Breaker QI,Q2,Q3,Q4 OPEN/CLOSE NA TBD Y Y IE Control Room See footnotes (d), (k), TBD TBD RCP's Position Panel RCP & (m)
A-31 See footnote (n) Lower CS Pump Pump IE,1W OPEN/CLOSE NA TBD Y Y IE Control Room See footnotes (d) and (k) TBD TBD Breaker Posi- Panel SPY tion A-32 See footnote (n) RNR Pump Pump IE,1W OPEN/CLOSE NA TBD Y Y IE Control Room See footnotes (d) and (k) TBD TBD Breaker Posi- Panel RHR tion A-33 See footnote (n) Valve Position TBD OPEN/CI.OSE TBD TBD TBD TBD TBD TBD See footnote (k) TBD TBD Limit Switches OPEN/NOT (various) OPEN CLOSF/NOT CLOSE A-34 See footnote (n) Safety Infec- IFI-260,266 0-200GPM Y Y Y Y IE Control Room Replace control room 1987 re- 1987 re-tion Pump Flow Panel SIS indicators with seismic fueling fueling qualified equipment outage outage A-35 See footnote (n) S/G Blowdown DRA-300,353 TBD TBD TBD TBD TBD IE Control Room TBD TBD TBD Radiation Panel RMS A-36 Manual Switchover Condensate CLI-113 Essentially Y Y Y Y IE Control Room Replace indicator with 1987 re- l987 re-to alternate water Storage Tank CLR-110, Top to Bot- Panel CP seismic qualified fueling fueling source on low level Level 111 tom equipment outage outage in CST See footnote (d)
Item Purpose Variable Tag No.s Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. Q A F S Location Schedule Schedule A-37 See footnote (n) Upper Contain- IFI-330,331 0-2500 CPM TBD TBD TBD TBD IE Control Room TBD TBD TBD ment Spray Panel SPY Flow
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Type B Variables: "those variables that provide information to indicate whether plant safety functions arc being accomplished. Plant safety functions are (1) reactivity control, (2) core cooling, (3) maintaining reactor coolant system integrity, and (4) maintaining containment integrity (including radioactive effluent control)." Note: The schedule and status of each instrument is for when all of the requirements of Regulatory Guide 1.97, Rev 3 will be met.
Item Purpose Variable Cat. Tag No.s Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. A F S Location Schedule Schedule B-1 Reactivity Neutron 1 NE-41A,41B, 0-120X full NA Y Y Y IF. Control Room See footnote (f) NA NA Control Flux 42A,42B, power Panel NIS 43A,438, 44A,44 8 B-2 Control Rod 3 Full in or NA NA NA NA NA Control Room None required NA NA Position not full in Panel B-3 RCS Soluble See item A-5 Boron Con-centrate B-4 RCS Cold See item A-6 Leg Temp-erature B-5 Core Cooling RCS Hot Sce item A-4 Lcg Water Temperature 8-6 RCS Cold See item A-6 Leg Water Temperature B-7 RCS Pressure See item A-2 B-B Core Exit See item A-25 Temperature B-9 Coolant Sec item A-24 Inventory B-10 Degrees of See item A-17 Subcooling
Item Purpose Variable Cat. Tag No.s Range B S Q S P Display Remarks/Action Req'd U-1 V-2 No. Q A F S Location Schedule Schedule B-11 Maintaining RCS Prcssure See item A-2 RCS Integrity B-12 Containment See item A-8 Sump Water Level B-13 Containment Sce items A-13 and A-14 Pressure B-14 Maintaining Containment 1 TBD CLOSFD TBD TBD TBD TBD TBD TBD Isolation Valve Limit TBD TBD Containment Isolation NOT CLOSFD S~itch information and Integrity Valve Posi- schedule will be provided tion (ex- with the update to this cluding report to be issued as check noted in thc cover letter valves) this enclosure B-IS Containment See items A-13 and A-14 Pressure
Type C Variables: "those variables that provide information to indicate the potential for being breached or the actual breach of the barriers to fission product releases. The barriers are (I) fuel cladding, (2) primary coolant pressure boundary, and (3) containment."
Note: The schedule and status for each instrument is for when all of the requirements of Regulatory Guide 1.97, Rev 3 will be met.
Item Purpose Variable Cat. Tag No.s Range E S Q S P Display Remarks/Action Req'd U-I U-2 No. A F S Location Schedule Schedule C-1 Fuel Cladding Core Exit See item A-25 Temperature C-2 Radioactive NSX-IOI,I03 Ii Tech Spec NA Y Y NA NA NA See footnote (h) NA concentra- Limit to 100 tion or Times Tech Radiation Spec Limit Level in Circulating Primary Coolant C-3 Analysis of 10cm Ci/ml See item C-2 Primary to 10cm Ci/
Coolant m or TID (Gamma 14844 Spectrum) Source Term in Coolant Volume C-4 Reactor Cool- RCS Pres- See item A-2 ant Pressure sure Boundary C-5 Containment See items A-13 and A-14 Prcssure C-6 Containment See item A-8 Sump Water Level C-7 Containment See item A-12 Area Radi-ation
Item Purpose Variable Cat. Tag No.s Range F. S Q S P Display Remarks/Action Req'd U-I V-2 No. Q A F S Location Schedule Schedule C-8 Fffluent 3 TBD TBD . NA NA NA NA TBD TBD TBD TBD Radioactiv-ity-Noble gas Ffflucnt from Con-denser Air Removal Sys-tem Exhaust C-9 Containment RCS Pressure See item A-2 C-IO Containment TBD TBD TBD TBD TBD TBD TBD TBD See footnote (k) TBD TBD llydrogen Concentra-tion C-11 Containment See items A-13 and A-14 Pressure C-12 Containment 2 TBD TBD NA NA NA NA IE Control Room See footnote (d) NA NA Effluent Panel MDG Radioactiv-ity-Noble gases from identified release points
Item Purpose Variable Cat. Tag No.s Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. Q A P S Location Schedule Schedule Effluent 2 TBD TBD TBD NA TBD NA TBD TBD Sce footnote (k) TBD TBD Radioactiv-ity-Noble
.Cases (from buildings or areas where penetra-tions and hatches are located, eg, secondary containment and AUX buildings that are in direct con-tact with primary containment
Type D Variables: "those variables that provi<lc information to indicate the operation of individual safety systems and other systems important to safety. These variables are to help the operator make appropriate decisions in using thc individual syst'ems important to safety in mitigating the the consequences of an accident." Note: The Schedule and Status for each instrument is for when all of the requirc-ments of Regulatory Guide 1.97, Rev 3 will be met.
Item Purpose Variable Cat. Tag No.s Range H S Q S P Display Remarks/Action Req'd U-I 0-2 No. Q Q A F S Location Schedule Schedule D-I RHR System RHR System See item A-21 Flow D-2 RHR Heat Fm- 2 ITR-311,321 TBD NA NA Y NA IF. Control Room Sce footnote (d) NA NA change Out- Panel RHR let Temp D-3a SI Systems Acrumu]ator 2 II.A-110-,111 0-133" wc Y NA IE Control Room Replace one transmitter / 1990 re- 1989 re-Tank Level 120,121> (wide range) Panel SIS tank with env. qualified fueling fueling 130,131, 105.8 to equipment and make wide outage outage 140,141 121.7 in. range (narrow range)
D-3b Accumulator 2 IPA-110,111 0-800 psig Y NA Y NA IF. Control Room Rcplacc onc transmitter / 1990 re- 1989 re-Tank Pres- 120,121, Panel SIS tank with env. qualified fueling fueling sure 130,131, equipment ou tagc outage 140, 14< 1 D-4 Accumulator 2 TBD Closed or TBD NA TBD NA TBD TBD Isolation Valve limit TBD TBD Tank Isola- Open switch information and tion Valve schedule will be provided Position with the update to this rcport to be issued as noted in the cover letter to this enclosure D-5 Boric Acid See item A-18 Charging Flow See item A-I D-6 Flow in HPI System D-7 Flow in LPI
.System Sec item A-21
Item Purpose Variable Cat. Tag No.s Range F. S Q S P Display Remarks/Action Req'd U-l U-2 No. Q Q A F S l.ocation Schedule Schedule D-B RWST I.evel See item A-16 D-9 Primary Cool- - RCP Status See item A-26 ant System D-10 Primary Sys- Sec item A-11 tem Safety Relief Valve Positions or Flow Thru or pressure in Relief Valve Lines Pressurizer Sec item A-10 Level D-12 Pressurizer See item A-27 Heater Sta-tus D-13 Quench Tank 3 NI,A-351 Top to NA NA NA NA IE Control Room None required Nh NA l.evel Bottom Panel PZR D-14 Quench Tank 3 NTA-351 50-750 F NA NA Nh NA IE Control Room Increase Range from 50'F 1987 re- 1987 re-Temperature Panel PRZ to 300'F to required fueling fueling 50-750 F outage outage D-15 Secondary Sys- S/0 I.evcl I BL1-110,120, Essentially Y Y Y Y IE Control Room Relocate transmitters 1990 re- 1989 re-Ccm (Steam 130,140 from cube Panel SG above containment floodup fueling fueling Generator) sheet c<> elevation. Replace outage outage separators indicators with seismic qualified equipment. See footnote (I)
D-16a SafeCy/Re- 2 TBD Closed-Not TBD NA TBD NA TBD TBD Valve Position limit TBD TBD lief Valve Closed switch information and Positions schedule will bc provided with the update to this report to be issued as noted in the cover letter to this enclosure
item Purpose Variable Cat. Tag No.s Range I S Q S P Display Remarks/Action Req'd U- I U-2 No. A F S Location Schedule Schedule D-16b Hain Steam HFC-IIO,III, 0-4x10 6 PPH Y NA Y NA IF. Control Room None required NA Flow 120,121, Panel SO 130,131, 140,141 D-17 Hain Fecd- FFC-210,211, 0-5xlO 6 PPH NA NA NA NA IF. Control Room None required NA NA water Flow 220,221, Panel BA 230.231, 240,241 D-18 Auxiliary Feed- Aux Fced- See item A-15 water System water Flow D-19 Condensatc See item A-36 Storage Tank Level D-20 Containmcnt Containment Sce item A-22 6 37 Cooling System Spray Flow D. C. Cook Plant Units 162 NA NA D-21 liest Removal do not have a Contain-by contain- ment liest Removal System, ment Neat Re- therefore this item does moval System not apply D-22 Containment 2 FTR-11,12,13, -40 to Y NA Y NA IE Control Room Replace RTD's with envi- 1990 re- 1989 re-Atmosphere 14,15,16, 400 F Panel A-14 ronmentaliy qualified fueling fueling Temperature 17,18,19, equipment. Increase range outage outage 20,21,22, from-40 to 300'F to as 23,24,?5. specified 26,27 D-23 Containment 2 See footnote (j)
Sump Mater Temperature
Item Purpose Variable Cat. Tag No.s Range -E S Q S P Display Remarks/Action Req'd U-1 U-2 No. A F S Location Schedule Schedule D-24 Chemical and Make up See item A-18 Volume Control Flow-In System D-25 Letdown Flow- See item A-19 Out D-26 Volume Con- 2 QLC-451>452 0-70" wc NA NA Y NA IE Control Room See footnote (d) NA NA trol Tank (essential- Panel BA Level ly top to bottom)
D-27 Cooling Water CCW water 2 CTR-410,415, TBD NA NA TBD NA TBD Control Room See footnote (d) TBD TBD System Temperature 420,425 Panel ESW to ESF Sys-tem D-28 CCW Flow to 2 CFI-410,419, TBD NA NA TBD NA IE Control Room See footnote (d) TBD TBD ESF System 420,429 Panel CCW D-29 Radwaste High Level 3 RLS-255>256 Top to Bot- NA NA NA NA IE Control Room None required NA Systems Radioactive tom Panel WDG Liquid Tank Level D-30 Radioactive 3 RPC-310,320, TBD NA NA NA NA IE Control Room None required NA NA Gas Holdup 330,340, Panel WDG Tank Pres- 350,360, sure 370,380 D-31 Ventilation Emergency 2 later Open-Closed TBD NA TBD NA TBD TBD Damper Position limit TBD TBD System Ventilation switch information and Damper Pos- schedule will be provided ition with the update to this report to be issued as noted in the cover letter to this enclosure
Item Purpose Variable Cat. Tag No.s Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. Q Q A F S Location Schedule Schedule Power Supplies Status of Standby Power and other Energy Sources Im-portant to Safety D-32a Diesel Cen 2 DGIAB 0-800A NA NA Y NA IE Control Room See footnote (d) NA NA Status DCICD Panel SA D-32b 4kv Safety 2 Bus T11A, 0-150V NA NA Y NA IE Control Room See footnote (d) NA NA Related Po- T11B, Panel SA wer Systems T11C, Status T11D D-32c 250V Battery 2 Battery AB 0-300V NA NA Y NA IE Control Room See footnote (d) NA NA Power System Battery CD Panel SA Status D-32d 120VAC Safe- 2 Channel I,II, 0-150V NA NA Y NA IE Control Room See footnote (d) NA NA ty Related III, IV Panel SA Power System Status D-32e Instrument 2 XPI-100 0-150psig NA NA Y NA NA Control Room These are mechanical NA NA Air Status X PI-50 0-100psig Panel SV devices no electrical XPI-20 0-60psig components XPI-85 0-160psig
Type E Variables: "those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and continually assessing such releases." Note: The schedule and status for each instrument is for when all of the requirements of Regulatory Guide 1.97, Rev. 3 will be met.
Iten Purpose Variable Cat. Tag No.s Range E S Q S P Display Remarks/Action Req'd U-1 U-2 No. A F S Location Schedule Schedule Containment Containment See item A-12 Radiation Area Radia-tion High Range E-2 Arcs Radiation Radiation 3 TBD TBD NA NA NA NA TBD TBD See footnote (k) TBD TBD Exposure Rate (in-side Build-ings or where areas of access is required to service equipment important to Safety E-3a Noble Cases . Containment 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k) TED TBD and vent Flow or Purge Rate Effluent E-3b Reactor 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k) TBD TBD Shield Building Annulus E-3c Aux Building 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k) TBD TBD E-3d Condenser 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k) TBD TBD Air Removal System Ex-haust E-3e Common 2 VRF-315 TBD TBD NA NA NA TBD TBD See footnote (k) TBD TBD Plant Vent
Item Purpose Variable Cat. Tag No.s Range E S 1) S P Display Remarks/Action Req'd U-1 V-2 No. A F S Location Schedule Schedule E-3f Vent from 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k) TBD TBD S/0 Safety Relief Valves OCher ident- 2 TBD TBD TBD NA NA NA TBD TBD See footnote (k) TBD TBD ified re-lease points F.-4 Particulates All identi- 3 NA TBD NA NA NA NA NA NA See footnote (k) TBD TBD and Halogens fied release points (ex-cept S/C Safety Re-lief valves and Conden-ser air re-moval System exhaust)
Sampling and onsite analysis E-5a Environ Radia- Airborne 3 NA TBD NA NA NA NA NA NA See footnote (k) TBD TBD tion and Radio- Radioacti-activity vity and Particulates sampling and analysis E-5b Plant and 3 NA TBD NA NA NA NA NA NA See footnote (k) TBD TBD Environs Radiation (Portable)
E-5c Plant and 3 NA TBD NA NA NA NA NA NA Sec footnote (k) TBD TBD Environs Radioacti-vity (Port-able)
Meteorology Wind tion Direc- 3 EFR-410,411, 420,421 0-360'A NA NA NA non Control
-IE Panel Fix Room None required NA NA
Item Purpose Variable Cat. Tag No.s Range E S O S P Display Remarks/Action Req'd U-l U-2 No. A F S Location Schedule Schedule E-7 Wind Speed 3 EFR-400,401, 0-100 mpH NA NA NA NA NON Control Room None required NA NA 402,403 -1E Panel Flx E-8 Estimation 3 ETR-400,401, TBD NA NA NA NA NON Control Room None required NA NA of Atmos- 402,403 -1E Panel Fix pheric Stability E-9a Accident Samp- Gross Acti- 3 TBD TBD NA NA NA NA NA NA None required NA NA ling Primary vity Coolant and Sump E-9b Gamma Spec- 3 TBD TBD NA NA NA NA NA NA None required NA NA trum F.-9c Boron Con- 3 TBD TBD NA NA NA NA NA NA None required NA NA tent E-9d Chloride 3 TBD TBD NA NA NA NA NA NA None required NA Content E-9f Dissolved 3 TBD TBD NA NA NA NA NA NA Hone required NA NA H2 or total gas E-9g (issolved 3 TBD TBD NA NA NA NA NA NA None required NA NA 2
E-9h pH 3 TBD TBD NA NA NA NA NA NA None required NA NA E-10a Containment H2 Content 3 TBD TBD NA NA NA NA NA NA None required NA NA Air 0 E-10b 2 Content 3 TBD TBD NA NA NA HA NA NA None required NA NA E-10c Gamma Spec- 3 TBD TBD NA NA NA NA NA NA None required NA NA trum
IV. FOOTNOTES DESIGNATING EXCEPTIONS TO REGULATORY GUIDE 1.97, REV. 3 (a) The automatic injection of boric acid into the RCS by the safety injection system following a postulated LOCA/HELB will be monitored and verified through the use of qualified instrumentation. In addition, since all sources of water for the safety injection system (Accumulators, Boric Acid Storage Tanks and Refueling Water Storage Tanks) are required by Technical Specifications to contain boric acid solution of a minimum concentration, the proper operation of the ECCS system ensures an adequate boron concentration in the reactor coolant to achieve and maintain the safe shutdown of the reactor core. The RCS soluble boron content is not expected to change rapidly, if at all, following the initial borating during the SI phase of an accident. Periodic analysis of RCS samples would detect any significant changes in boron concentration. Instrumentation to continuously monitor RCS soluble boron concentration is not required since periodic analysis of RCS grab samples is adequate for verification of reactivity control.
(b) Redundancy not required per NUREG 0737 requirements.
(c) Seismic qualification not required per NUREG 0737 requirements.
(d) All equipment is located in mild environment, therefore environmental qualification is not required.
(e) Lack of lower containment spray flow monitoring instrumentation will not deter the operator's ability to determine adverse containment conditions (ACC). ACC can be monitored by looking at items such as containment pressure. If we see containment pressure conditions different than what is expected, then we can confirm whether ACC is due to a lack of spray flow by the monitoring of containment spray pump .discharge pressure.
(f) The neutron flux monitors are not required for LOCA/HELB mitigation, therefore their environmental qualification is not required. Following a LOCA/HELB, reactivity control to accomplish reactor shutdown is automatically achieved and maintained by a reactor SCRAM and the injection of boric acid by ECCS. This can be verified through control rod position indications and analysis of RCS grab samples. Footnote (h) is also applicable.
(g) Scheduled for upgrade as described in AEP:NRC: 0761 C (h) Instrumentation to continuously monitor RCS radioactivity is not required. Periodic analysis of RCS grab samples is adequate to detect deterioration of fuel cladding. Indicative of an inadequate core cooling (ICC) event, fast deterioration of fuel cladding could be detected by sensing the ICC conditions through diverse instrumentation (i.e., RVLIS, CET's, TSAT meter).
(i) Redundancy is accomplished by the measurement of diverse variables with fully qualified equipment. Auxiliary Feedwater Flow is backed up by S/G level (narrow range).
(j) Containment Sump Water Temperature will give no information required to mitigate and determine the consequences of an accident. Containment Sump Level, Atmosphere Temperature and pressure are adequate for operators to determine containment conditions. Therefore, measurement of Containment Sump Water Temperature is not required.
(k) This information will be provided with our update to this report to be issued as noted in the cover letter to this enclosure.
(1) INTENTIONALLY LEFT BLANK (m) Redundancy is accomplished by verifying pump flow from qualified instrumentation.
(n) This item may be deleted from the Type A variable list after further review of the DCCNP EOP's. If this occurs, the variable will be recategorized accordingly and the appropriate actions taken. The update to this report, to be submitted as noted in the cover letter to this enclosure, will reflect any changes of this nature.
p.