ML17334A919

Implementation Plan of Reg Guide 1.97,Rev 3 for Donald C Cook Nuclear Plant Units 1 & 2, Status Rept

ML17334A919
Person / Time
Site:	Cook
Issue date:	10/15/1985
From:	INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17334A918	List: ML17334A917 ML17334A919
References
RTR-REGGD-01.097, RTR-REGGD-1.097 AEP:NRC:07730, AEP:NRC:7730, PROC-851015, NUDOCS 8510220255
Download: ML17334A919 (34)

Text

ENCLOSURE TO AEP:NRC:07730 STATUS REPORT IMPLEMENTATION PLAN OF REGULATORY GUIDE 1.97, REVISION 3, FOR THE DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2

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ENCLOSURE TO, AEP: N~07730 E

TABLE OF CONTENTS I. Background II. Status Report III. Tables IV. Footnotes

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ENCLOSURE TO EEP:NR7730

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In August 1984, AEPSC contracted the engineering consulting firm of DiBenedetto, Farwell & Hendricks 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 preliminary Status Report (AEP:NRC:0773J dated February 28, 1985), based on preliminary findings by our consultant, was submitted to the NRC staff. A final rep'ort was to have been issued by our consultant by June, 1985, but because of various delays, the consultant's report is not available at this time. Work has progressed well enough so that we believe a final submittal, as committed to in AEP:NRC:0773J, can be made. Any inconsistencies between the consultant's final report and this submittal will be resolved and, if necessary, this submittal will be revised accordingly.

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 a schedule for each type A,B,C,D, and E variable listed in Regulatory Guide 1.97, Revision 3. The definitions of these variables are provided in Section III. 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. 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 and 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 is provided in the column labeled "variable."

2. Environmental uglification Instruments reported as environmentally qualified (marked "Y" in the column labeled "EQ") are pl.,ned to meet the provisions of 10 CFR 50.49. As allowed by 10 CFR 50.49(k), original DCCNP instrumentation located in a potentially harsh environment has been qualified, as a minimum, 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.

Further, equipment located in a mild environment is not environmentally qualif'ed. We believe the above position to be consistent with the current licensing status of the DCCNP.

ENCLOSURE TO AEP:N~7730

3. Seismic uglification Instruments reported as seismically qualified (i.e., marked "Y" in the column labeled "SQ") are planned to meet the provisions of DCCNP Updated FSAR p. 7.2-12 dated July 1982 (i.e., protection grade equipment is designed such that, for a design basis earthquake, the equipment will not lose its

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capability to perform its design objective, to shut the plant the plant down and/or maintain the unit in a safe shutdown condition.) Typical equipment of this type originally instal-led at DCCNP was seismically tested by Westinghouse Electric Corporation as documented in WCAP-7397-L, "Topical Report Seismic Testing of Electrical and Control Equipment" dated January, 1970. 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 IEEE Std. 344-1975 unless there are sound reasons to the contrary. Again, we believe this position to be consistent with the current licensing status of the DCCNP.

4. ualit Assurance Instruments reported as meeting quality assurance requirements (i.e., marked "Y" 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 dated July, 1985. We believe this program, as described, satisfies the requirements of 10 CFR 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 dated July, 1985.

Instruments reported as meeting the single failure criterion or redundancy requirements (i.e., marked "Y" 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 DCCNP Updated FSAR p.

7.2-4 dated July, 1982. Physical separation requirements for redundant Post Accident Monitoring Instrumentation channels will be established in a manner consistent with the applica-tion of separation criteria for existing plant IE instrumenta-tion & control circuits. The extent of conformance to Regula-tory 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 require-ments (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 250V DC buses as described in DCCNP Updated FSAR Sections 8.1 and 8.3 dated July, 1982.

ENCLOSURE TO .AEP:N~7730

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 current best configuration estimate 'f The implementation schedule provided for each variable is the the completion of the final 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 some items listed may require revision or deletion, 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 response to Regulatory Guide 1.97 is by the end of the Unit 2 refueling outage presently scheduled for 1989.

It is noted that although many variables presently listed are measured with fully functional instrumentation, they are not considered operational in the sense that they meet Reg. Guide 1.97 requirements. As noted previously in this document, we have not yet updated all instruments and associated equipment to meet Reg. Guide 1.97 requirements. In addition, it should be noted 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.

Because of the additional information obtained after our preliminary submittal in February, 1985, and discussions with the NRC staff and their consultant (EG&G), there are many differences between our preliminary submittal and this final submittal. All item numbers in the tables in Section III have been retained, regardless of whether they are used in order to provide easy .cross referencing between the preliminary .and final reports.

Major changes involve reassigning variables from Type A to other classifications due to further evaluation of plant EOP's and completion of information not available at the time of our original submittal. Other miscellaneous corrections and revisions have been made due to the more complete information that is now available.

'ENCLOSURE TO AEWNRC:07730 III. TABLES These tables represent the status of the Donald C. Cook Nuclear Plant when we will 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.

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 10 CFR 50.49, whose requirements may be different.

Type h Variables: "those variables to be monitored that provide the primary information required to permit the control room manually controlled actions for which no automatic control is provided and that are required for safety systems operator to take specific safety functions for design basis accident events. to accomplish their Primary information is information that is essential for the direct accomplishment of the specified safety funtions; it does not include those variables that sre associated with contingency actions that may also be identified in written procedures." Note: These variables are plant-specific and based on review of Cook Nuclear Plant Emergency Operating Procedures (EOP's) plus anticipated future changes to the KOP's. the D. C.

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 Nos. Range E S S P Display Remarks/Action Req'd U-1 No.

Q U-2 Q Q h F S Location Schedule Schedule A-1 Maintain Pressur- Centrifigal IFI-51,52, 0-200 CPM IE Control Room Qualify or replace control 1987 're- 1987 re-izer Level during Chg Pump Flow 53,54 Panel SIS room indicators with fueling fueling S/C Tube rupture seismically qualified outage outage equipment h-4'OT A-2 Manual Trip of RC RCS Pressure NPS-121,122 0-3000psig Y Y Y Y IE Control Room Qualify or replace control 1987 re- 1987 re-Pumps based on RCS (wide range) Panel RHR room recorder with pressure fueling fueling seismically qualified outage outage equipment h-3 USED NOT USED A-5 NOT USED h-6 NOT USED h-7 Determination of S/C Pressure MPP-210,211. 0-1200psig Y Y Y Y IE Control Room Qualify or replace control 1987 re- 1987 re-required core exit 212,220, Panel SC room indicators with fueling fueling temperature by S/C 221,222, seismically qualfied outage outage Pressure 230,231 equipment

'32,240, 241.242 ENCLOSURE TO AEPINRC:07730 Page 7

Item Purpose Variable Tag Nos. Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. A P S Location Schedule Schedule A-8 Determination of Containment NLA-310 589.5 to Y Y Y Y IE Control Room Qualify or replace control 1987 re- 1987 re-adverse containment Sump Level NLI-311,320> 614 ft. el- Panel RHR room indicators vith fueling fueling 321 evation seismically qualified outage outage (bottom of equipment sump to max flood level) h-9 Hanual Reduction of S/C Level BLP-110,111> From belov Y Y Y Y IE Control Room Qualify or replace control 1987 re- 1987 re-ECCS Plov Nerrrov range 112,120, 1st stage Panel SC room indicators and/or fueling fueling (Secondary heat 121.122> separator to recorders vith seismic- outage outage sink capability) 130,131, 2nd stage ally qualified equipment 132,140. separator 141>142 A-10 Manual Reduction of Pressuriaer NLP-151,152> 0-100X Y Y Y Y IE Control Room Qualify or replace control 1987 re- 1987 re-ECCS Flov Level 153 (96X of Panel PZR room indicators and/or, fueling fueling Total (NLP-151 also recorders vith seis- outage outage Volume) HSD) mically qualified equipment h-11 NOT USED h-12 Determination of Containment VRA-1310, 1 R/)R to Y NA Y Y IE Control Room See footnote (c) Nh NA adverse containment brea Radiation 1410, lxlo R/HR Panel RHS Honitor High (Unit 1)

Range 2310, 2410 (Unit 2)

A-13 Manually establish Containment PPP-300,301, -5 to +12 NA Y Y Y IE Control Room Qualify or replace 1987 re- 1987 re-or trip containment Pressure 302,303 psig Panel SPY indicators vith fueling fueling spray (Narrov range) seismically qualified outage outage equipment See footnote (d) h-14 NOT USED ENCLOSURE TO AEPINRC:07730 Page 8

Item Purpose Variable Tag Nos. Range E S Q S P Display Remarks/Action Req'd IJ-1 U-2 No. Q h F S Location Schedule Schedule A-15 Manual Reduction of Auxiliary FFI-210,220, 0-250 KPPH Y Y Y Y IE Control Room Redundancy provided by 1987 re- 1987 re-ECCS Flow Peedwater Flow 230,240 Panel SC diverse variable - S/C fueling fueling, (Secondary heat narrow range level which outage outage sink capability) is qualified. Qualify or replace indicators, power supplies, and square root converters with seismical ly qualified equipment. Powe r from IE source.

' re- 1987 re-A-16 Manual Transfer to RUST Level ILS-950,951 essentially NA Y Y IE Control Room Qualify or replace 1987 cold leg recircula- Top 'to Panel SPY indicators and/or fueling fueling tion in low level Bottom recorders with seismic- outage outage in RUST (IOOZ of ally qualified equipment.

Total Also see footnote (d)

Volume)

A-17 Manual Trip or re- Degrees Sub- Nh 0-199'F sub- Y Nh Y Nh IE Control Room See footnotes (b) 6 (c) NA NA duction of Press- cooling cooling Panel BA which apply beyond the urirer Spray and 0-199'F isolating devices ECCS Flow Superheat A-18 NOT USED A-19 NOT USED A-20 NOT USED h-21 NOT USED h-22 NOT USED h-23 NOT USED h-24 NOT USED A-25 Manual Reduction Core Exit T/C 1-65 200-2300 F Y Y Y IE Control Room All required cables. NA See foot-of ECCS Flow T/C's Panel FI connectors, indicators, note (g)

(IJ-1) Panel signal processing RMS (U-2) equipment to be replaced with qualified equipment (Unit 2 only. No action required Unit 1)

ENCLOSURE TO AEP:NRC:07730 Page 9

Item Purpose Variable Tag Nos. Range E S Q S P Display . Remarks/Action Req'd U-l U-2 No. A F S Location Schedule Schedule h-26 NOT USED A-27 NOT USED h-28 Manual trip of CCP Breaker Pump IE,IW OPEN/CLOSE Nh Y Y Y IE Control Room Qualify or replace End of End of RCP's Status Panel Bh control room indicators 1988 1988 with seismically qualified equipment See footnotes (d) & (m)

A-29 Manual trip of SI Pump Pump 1N,IS OPEN/CLOSE NA Y Y Y IE Control Room Qualify or replace End of End of RCP's Breaker Status Panel SIS control room indicators 1988 1988 with seismically qualified equipment See footnotes (d) & (m)

A-30 NOT USED h-31 NOT USED h-32 NOT USED h-33 NOT USED h-34 Manual Trip of Safety In]ec- IFI-260.266 0-800CPM Nh Y Y Y IE Control Room Qualify or replace 1987 re- 1987 re-RCP's cion Pump Flow Panel SIS control room indicators fueling fueling with seismically outage outage qualified equipment.

See footnote (d)

A-35 Identify Ruptured S/0 Blowdown DRA-300,353 10-10E06 Nh Y Y Y IE Control Room Qualify or replace all 1988 re- 1989 re-Stcam Generator Radiation CPM Panel RMS components with seismic- fueling fueling ally qualified equipment outage outage and power from IE source.

See footnote (d)

A-36 NOT USED A-37 NOT USED ENCLOSURE TO AEP:NRCI07730

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Type B Variables: "those variables that provide information to indicate whether plant safety functions are being accomplished. Plant safety functions are (1) reactivity control, (2) core cooling, (3) maintaining reactor coolant system integrity, and (4) maintaining containmenr 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 Nos. Range E S . Q S P Display Remarks/Action Req'd U-l 0-2 No. A F S Location Schedule Schedule B-1 Reactivity Neutron 1 NE-41A,41'2A,42B.

0-1202 full NA Y Y Y IE Control Room None Required NA NA Control Flux power Panel NIS See footnote (f) 43A,438, 44A,448 B-2 Control Rod 3 CA1-8 I CB1-4 Full in or NA Nh NA Nh NA Control Room None required NA NA Position CC1-8, CDI-9 not full in Panel RC SA1-8, 5B1-8 B-3 RCS Soluble 3 NSX-101,103 Nh NA NA Nh NA NA See Item C-2 NA Boron Con- and footnote (a) centrate B-4 RCS Cold 1 NTR-210,220, 0-700 F Y Y Y Y IE Control Room Qualify or replace 1987 re- 1987 re-Leg Temp- 230,240 Panel DTU recorders with seismic- fueling fueling erature ally qualified equipment outage outage B-5 Core Cooling RCS Hot 1 NTR-110,120, 0-700'F Y Y Y Y IE Control Room Qualify or replace record- 1987 rc- 1987 re-Leg Mater 130.140 Panel DTU ers with seismically fueling fueling Temperature qualified equipment outage outage B-6 RCS Cold 1 Sce item B-4 Leg Mater Temperature B-7 RCS Pressure Sce item A-2 B-8 Core Exit See item h-25 Temperature ENCLOSURE TO AEP:NRC107730 Page 11

Item Purpose Variable Cat. Tag Nos. Range E S Q S P Display' Remarks/Action Req'd U-1 U-2 No. F S Location Schedule Schedule B-9 Coolant NLI-110,111 Top of head Y Y Y Y IE Control Room None required NA NA Inventory 120,121, vent piping Panel SIS 130,131 to bottom of vessel (1002 of Volume) 8-10 Degrees of See item h-17 Subcooling B-ll Maintaining RCS Pressure See item h-2 RCS Integrity B-12 Containment See item A-8 Sump Water Level B-13 Containment 1 PPA-310,312 -5 to 36psig NA Y Y Y IE Control Room Qualify or replace 1987 re- 1987 re-Pressure Panel SPY Indicators/recorders, fueling fueling (Wide Range) vith seismically outage outage qualified equipment.

Also see item h-13 for narrov range Sec footnote (d)

B-IA Maintaining Containment 1 See listing CLOSED - Y Y Y Y IE Control Room Replace Limit svitches 1988 re- 1989 re-Containment Isolation in Attach- NOT CLOSED Panels IV, vith env 6 seismically fueling fueling Integrity Valve Posi- ment 1 to BA,SIS,SPY qualified devices as outage outage tion (ex- these tables noted in Attachments 1 6 cluding 2 to these tables.

check Qualify or replace valves) control room indicators vith seismically quali-fied equipment.

B-15 Containment Pressure See items h-13 and B-13 ENCLOSURE TO AEP:NRC:07730 Page 12

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 (1) 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 Nos. Range E S Q S P . Display Remarks/Action Req'd U-l U-2 No. Q Q A P S Location Schedule Schedule C-1 Puel Cladding Core Eric See item A-25 Temperature C-2 Radioactive 1 NSX-101,103 NA Y Y Y Y Y NA See footnote (h) 1987 re- 1987 re-concentra- m Replace solenoid valves refueling refueling tion or with seismically and outage outage Radiation environmentally qualified Level in equipment Circulating Primary Coolant C-3 Analysis of See item C-2 Primary Coolant (Gamma Spectrum)

C-4 Reactor Cool- RCS Pres- See item A-2 ant Pressure sure .

Boundary C-5 Containment See items A-13 and 8-13 Pressure C-6 Containment See item A-8 Sump Water Level C-7 Containment See item A-12 Area Radi-ation ENCLOSURE TO AEPiNRC:07730 Page 13

item Purpose Variable Cat. Tag Nos. Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. Q Q A P S Location Schedule Schedule C-g Effluent 3 - SRA-1900 IOE-07 to NA NA NA NA NA Control Room No accion required NA Radioactiv- (Unit I IOE03 CT-I Control ity-Noble SRA-2900 p.Ci/cc Terminal gas Effluent (Unit 2) from Con-denser Air Removal Sys-tem Exhaust C-9 Containment RCS Pressure Sce item h-2 C-IO Containment ESR-I NA NA Y Y Y IE NA See footnote (d) NA NA Hydrogen thru 9 No action required Concentra-tion C-l I Containment See items A-13 and B-I3 Pressure C-12 Containment ERS-1300 'OE-07 to NA NA NA NA NA Panel WDG See footnote (d) NA NA Effluent 1400(Unit IOE05 No Action Required Radioactiv- I) /ICi/cc ity-Noble ERS-2300, gases from 2400 (Unit identified 2) release points ENCLOSURE TO AEP:NRC:07730 Page 14

Item Purpose Variable Cat. Tag Nos. Range E S Q S F Display "

Remarks/Action Req'd U-I U-2 No. Q Q A F S Location Schedule Schedule C-13 Effluenc SEE ITEN C-12 Radioactiv- ~ ~

icy-Noble Cases (from buildings or areas vhere penecra-cions and hacches are located, eg, secondary containment and AUX buildings chat are in direct con-cacc vich primary containment ENCLOSURE TO AEP:NRC107730 Page 15

Type D Variables: "those variables that provide 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 the individual systems 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 require-ments of Regulatory Guide 1.97, Rev 3 will be met.

Item Purpose Variable Cat. Tag Nos. Range E S Q S P Display Remarks/Action Req'd U-I U-2 No. Q Q A F S Location Schedule Schedule D-I RHR System IU1R System 2 IPI-310,311, 0-1500 CPH Y NA Y Nh Nh Control Room No Action Required NA Flow 320,321 0-5500 CPH Panel RHR D-2 RHR Heat Ex- 2 ITR-311,321 50-400 F Y NA Y NA Nh Control Room Replace RTD's with 1987 re- 1987 re-change Out- Panel RHR env. qualified equip- fueling fueling let Temp ment. See footnote (p) outage outage D-3a SI Systems Accumulator 2 ILA-IIO-,III 0-133" wc Y NA Y Nh NA Control Room Replace one wide range 1988 re- 1989 re-Tank Level 120,121, (wide range) Panel SIS transmitter with env. fueling fueling 130,131, (522 of qualified equipment. See outage outage 140,141 Total footnote (p)

Volume) 105.8 to

-121.7 in.

(narrow range)

(7.5X of Total Volume)

D-3b Accumulator 2 IPA-110.111, 0-800 psig Y NA Y NA NA Control Room Replace one transmitter/ 1988 re- 1989 re-Tank Pres'- 120,121, Panel SIS tank with env. qualified fueling fueling sure 130,131. equipment outage outage 140,141 D-4 Accumulator 2 IM0-110,120, Closed or NA NA Y NA NA Control Room None Required 1987 re- 1987 re-Tank Isola- 130,140 Open Panel SIS See footnote (r) fueling fueling tion Valve outage outage Position ENCLOSURE TO AEP:NRC:07730 Page 16

Item Purpose Variable Cat. Tag Nos. Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. Q Q A F S Location Schedule Schedule D-5 Boric Acid See item D-24 Charging Flov D-6 Flov in HPI See item h-1 System D-7 Flov in LPI See item D-1 System D-8 RWST Level See item A-16 D-9 Primary Cool- RCP Status 3 QI,Q2.Q3,Q4 0-1200A NA NA NA NA NA Control Room No Action Required NA NA anc System Panel RCP D-10 Primary Sys- 2 QR-107 A,BE Nh Y NA Y NA NA Concrol Room See footnote (b) NA NA tem Safety C,D P~nel RC No hccion Required Relief Valve Positions or Flov Thru or pressure in Relief Valve Lines D-11 Pressurizer See item h-10 Level D-12 Pressurizer 2 Croup AI,A2, ON/OFF NA NA Y Nh NA Control Room See footnote (d) NA NA Heater Sca- A3,C1,C2,C3 Panel PZR No Action Required tus D-13 Qu5nch Tank 3 NLA-351 Essencially NA NA NA NA NA Control Room None required NA NA Level Top to Panel PZR Sce footnote (p)

Bottom (74Z of Total Volume)

D-14 Quench Tank 3 NTA-351 50-750'F NA NA NA NA NA Control Room Increase Range from 50'F 1987 re- 1987 re-Temperature Panel PRZ

)Q;$ to required fueling fueling g outage oucage ENCLOSURE TO AEP:NRCI07730 Page 17

Item Purpose Variable Cat. Tag Nos. Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. Q Q A F S Location Schedule Schedule D-14 a Quench Tank 3. NPA-351 -10 to 100 NA NA Nh NA NA Control Room None Required NA NA Pressure psig Panel PRE D-15 Secondary Sys- S/0 Level 1 BLI-110 '20> From 12" NA NA Y Y NA Control Room None required See NA tern (Steam 130>140 above cube Panel SG footnote (i)

Generator) (vide range) sheec to sep-arators D-1&a Safety/Re- See Item D-16b for lief Valve alternate instrumentation Positions D-16b Main Steam 2 MFC-110,111, 0-4x10 6 PPH Y NA Y NA NA Control Room Hone required NA NA Flow 120,121, Panel SC 130,131, 140,141 D-17 Mein Feed- 3 FFC-210,211 0-Sx10 6 PPH NA NA NA NA NA Control Room None required NA water Flow '20,221, Panel BA 230,231, 240 F 241 D-18 Auxiliary Feed- Aux Feed- See item h-15 vacer System vater Flow D-19 Condensate 1 CLI-113 Essentially NA Y Y Y IE Control Panel Qualify or replace 1987 re- 1987 re-Scorage CLR-110> Top to Bot- instruments vith seismic- fueling fueling Tank Level 111 tom (952 ally qualified equipment. outage outage Total See footnotes (d) &

Volume) (p) (2 channels only)

D-20 Containment Containment 2 IFI-,330.331 0-200CPM NA NA Y NA NA Control Room No hccion Required NA NA I

Cooling System Spray Flov (Upper con- Panel SPY See footnotes (d) & (e) tainment)

D-21 Heat Removal D. C. Cook Plant Units 1&2 Nh NA by contain- do noc have a Concain-ment Heat Re- menc Heat Removal System, moval System therefore this item does noc apply ENCLOSURE TO AEPliVRC:07730 Page 18

Item Purpose Variable Cat. Tag Nos. Range E S Q S P Display Remarks/Action Req'd U-l U-2 No. Q Q h F S Location Schedule Schedule D-22 Containment 2 ETR-11,12,13, 0 to Y Nh Y NA Nh Control Room Replace six (6) tech spec 1988 re- 1989 re-Atmosphere 14,15 '6, 400 F Panel h-14 related RTD's with envi- fueling fueling Temperature 17,18,19, ronmentally qualified outage outage 20,21,22, equipment. Increase range 23,24,25, from 0 to 300 F to as 26,27 specified.

D-23 Containment 2 No Action Required See Sump 'Mater footnote (j)

Temperature D-24 Chemical and Make up 2 QFI-200 0-200 GPM NA NA Y NA NA Control Room No Action Required See NA NA Volume Control Flow-In Panel BA footnote (d)

System D-25 Letdown Flow 2 QFI-301 0-200 GPM NA NA Y NA NA Control Room No Action Required, NA NA Out Panel BA and See footnote (d)

HSD D-26 Volume Con- 2 QLC-451,452 Essential- Nh NA Y NA NA Control Room No Action Required NA NA trol Tank ly top to Panel BA See footnote (d) & (p)

Level bottom (65X of Total Volume)

D-27 Cooling Hater CCM water 2 CTR-410.415. 0-200 F Nh NA Y Nh NA Control Room No Action Required NA NA System Temperature 420,425 Panel ESN See footnote (d) to ESF Sys-tem D-28 CCM Flow to 2 CFI-410,419, 0-10000GPM Nh NA Y Nh Nh Control Room No Action Required Nh Nh ESF System 420,429 0-6000GPM Panel CCN See footnote (d)

D-29 Radwaste High Level 3 RLS-255 '56 Essentially Nh NA NA Nh NA Panel NDG None required NA Systems Radioactive Top to Bot- See footnote (p)

Liquid Tank tom (84X of Level Total Volume)

ENCLOSURE TO AEP:NRC:07730 Page 19

Item Purpose ." Variable Cat. Tag Nos. Range E S g S P Display Remarks/Action Req'd U-l U-2 No. A F S Location Schedule Schedule D-30 Radioactive RPC-310,320, 0-225 psig Panel 3 Nh Hh Nh Nh NA QDC Increase range from 0-150 1987 re- 1987 re-Cas Holdup 330,340, psig to 0-225 psig fueling fueling Tank Pres- 350,360, As specified outage outage sure 370,380 D-31 Ventilation Emergency 2 VCR-201 thru Open-Closed Y NA Y Nh Nh Control Room Replace Limit Switches 1988 re- 1989 re-System Ventilation 207 Panel IV VCR-201 6 202 with env. fueling fueling Damper Pos- VCR-207 qualified equipment. outage ition on Control Footnote (d) applies to Room Panel VCR-203 thru 207.

SPY See footnote (s)

Power Supplies Status of Standby Power. and other Energy Sources Im-portant to Safety D-32a Diesel Cen 2 DCIAB 0-800A Nh Nh Y Nh HA Control Room See footnote (d) NA NA Status DC1CD Panel Sh No Action Required D-32b 4kv Safety 2 Bus Tllh. 0-150V Nh NA Y Nh Nh Control Room See footnote (d) Nh Nh Related Po- T11B, Panel SA No Action Required wer Systems T11C, Status T11D D-32c 250V Battery 2 Battery AB 0-300V NA NA Y NA NA Control Room See footnote (d) NA NA Power System Battery CD Panel SA No Action Required Status D-32d 120VAC Safe- 2 Channel I,II, 0-150V NA NA Y NA NA Control Room See footnote (d) NA ty Related III, IV Panel SA No Action Required Power System Status D-32e Instrument 2,XP I-100 0-150psig Nh Nh Y NA NA Control Room These are mechanical NA NA Air Status XP I-50 0-100psig Panel SV devices no electrical XPI-20 0-60psig components No Action XPI-85 0-160psig Required ENCLOSURE TO AEP:.NRC107730 Page 20

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.

Item Purpose Variable Cat. Tag Nos. Range E S g S P Display Remarks/Action Req'd U-l U-2 I No. A F S Location Schedule Schedule E-1 Containment Containment See item A-12 Radiation Area Radia-tion High Range E-2 Area Radiation Radiation 3 VRC-301 IOE-01 to NA NA NA'A NA Control Room None required NA Exposure NRA-340 10E04 mR/hr Panel RHS See footnote (p)

Rate (in- RRA-322 side build-ings or

~here areas of access are required to service equipment important to safety)

E-3a Noble Cases Containment SEE ITEH E-3e and vent. Flow or Purge Rate Effluent E-3b Reactor SEE ITEN E-3e Shield Building Annulus, E-3c Aux Building 2 SEE ITEH E-3e E-3d Condenser 2 SFR-1900 10E-06 to NA NA Y NA NA See footnotes NA Air Removal (Unit 1) 10E03 (d) 4 (P)

System Ex- SFR-2900 +Ci/cc haust (Unit 2) 0-2000 SFR-401 scfm ENCLOSURE TO AEP I NRC107730 Page 21

Item Purpose Variable Cat. Tag Nos. Range E S Q S P Display Remarks/Action Req'd U-l.- U-2 No. A F S Location Schedule Schedule E-3e Common 2 VRS-1500 10E-07 to NA NA Y Nh Nh Control Room None Required NA NA Plant Vent (Unit 1) 10E05 CT-1 Control See footnote (d)

VRS-2500 pCi/cc Terminal (Unit 2)

VRF-315 0-200K scfm E-3f Vent from 2 HRA-1600 3 to 20E05 Y Nh Y NA Nh Control Room None Required NA NA S/C Safety 1700 p,Ci/cc Panel RHS Relief (Unit 1)

Valves HRA-2600 2700 (Unit 2)

E-3g Other ident- 2 SRA-1800'Unit 108-07 to Nh NA Y NA NA Control Room None Required NA ified re- 1) 10E03 Panel FI See footnote (d) lease points SRA-2800 plCI/cc (Unit 2)

SFR-201 0-1000 scfm E-4 Particulates All identi- 3 See Item E-3e and Balogens fied release points (ex-cept S/C Safety Re-lief valves and Conden-ser air'e-moval System exhaust)

Sampling and onsite analysis Environ Radia- Airborne Nh 10-9 to NA NA NA NA NA NA None Required Nh tion and Radio- Radioacti- 10-3 activity vity and P Ci/cc Particulates (minimum) sampling and analysis (portable)'

ENCLOSURE TO AEPINRC:07730 Page 22

Iten Purpose Variable Cat. Tag Nos. Range E S S P Display Renarks/Action Req'd U-l 0-2 Ho+

Q A i S Location Schedule Schedule E-5b Plant and 3 Nh 10E-3 to Nh Nh Nh Hh Nh NA None required Nh NA Environs 10E4 Radiation R/HR (Portable) (ninimun)

I E-Sc Plant and 3 Nh NA NA Nh Nh HA Nh Nh None required Nh NA Environs I Radioacti-vity (Port-able)

E-6 Meteorology Wind Direc- 3 EFR-410,411, 0-360 NA NA Nh Hh Nh Control Roon None required Nh NA cion 420,421 Panel Fix E-7 'Wind Speed 3 EPR-400,401, 0-100 nph NA NA NA Nh Nh Control Roon None required Nh Nh 402,403 Panel Plx E-S Estination 3 ETR-400,401, -35 to 50'C Nh NA NA NA NA Control Roon None required NA of htnos- ETQ-401,402 Panel Fix pheric 403,404 Stability E-9a Accident Sanp- Cross Acti<< SEE ITEM C-2 ling Prinary v icy Coolant and Suep E-9b Canna Spec- SEE ITEM C-3 trun E-9c Boron Con- SEE ITEM B-3 tent E-9d Chloride 3 HSX-101.103 HA HA HA NA HA NA HA SEE ITEM C-2 Nh Content E-9f Dissolved 3 NSX-101,103 0-2000 cc/ Nh Nh NA NA Nh Nh SEE ITEM C-2 NA NA H2 or total kg gas ENCLOSVRE TO AEP:NRC:07730 Page 23

O.

Item Purpose Variable Cat. Tag Nos. Range E S Q S P Display Remarks/Action Req'd U-l U-2 Ho+ h F S Location Schedule Schedule E-9g Bissolved 3 NSX-101, 0-20 ppm NA Nh Nh Nh Hh NA SEE ITEM C-2 NA Nh 2 103 E-9h pH 3 NSX-101 103

'.0pH to 8.0 Nh NA NA HA NA Nh SEE ITEM C-2 Nh NA E-10a Containment H 2

Content 3 ESX-001 Nh NA Nh NA NA Nh NA None required NA NA Air E-10b 0 2 Content 3 HA NA Nh Nh HA HA NA NA Hone required NA NA See footnote (q)

E-loc Gamma Spec- 3 ESX-001 NA NA NA HA NA NA NA None required NA NA tram ENCLOSURE TO AEP:NRC:07730 Page 24

ATTACHHENT NO.l TO TYPE B VARIABLES TABLE ITEH NO. B-14 CONTAINHENT ISOLATION VALVES Plant ID I Channel Plant ID I Channel I I CCR-455 ICCV to Reactor Supports ECR-10 ICntnsent. H2 Sssple & Return Valves CCR-456 ICCV froa Reactor Supports ECR. 11 ICntnsvnt 82 Saaple & Return Valves CCR-457 ICCV frOs ReaCtOr SuppOrto ECR-12 ICntnsent H2 Sasple & Return Valves CCR-460 ICCV fros Excess Letdovn Hx ECR-13 ICntnsent H2 Sasple & Return Valves CCR-462 ICCV to Excess Letdovn Hx ECR-14 ICntnsent H2 Sasple & Return Valves DCR-201 IRC Drain Tink to Vent Header ECR-15 ICntnsent H2 Sasple & Return Valves DCR.204 IRC Drain Tank to Gas Analyzer

'CR-16 ICntnsent H2 Sasple & Return Valves DCR-205 IRC Drain Tank Suction Isolation ECR-17 ICntnsent H2 Saaple & Return Valves DCR-206 IRC Drain Tank Suction isolation ECR-18 ICntneent H2 Sasple & Return Valves DCR-207 IHitrogen Supply to RC Drain Tank ECR-19 ICntnaent H2 Sssple & Return Valves DCR-301 IS/G Slovdovn Saaple Isolation ECR-20 ICntnsent H2 Saaple & Return Valves OCR-302 IS/G Blovdovn Saaple Isolation ECR-21 ICntnsent H2 Sssple & Return Valves DCR-303 IS/6 Blovdovn Sasple isolation ECR-22 ICntnaent H2 Sasple & Return Valves DCR 304 IS/G Slovdovn Sasple Isolation ECR-24 ICntnsent H2 Sasple & Return Valves DCR-310 IS/G il, i2, i3 & i4 Blovdovn Valves ECR-23 ICntnsent H2 Sasple & Return Valves DCR-320 IS/G il, i2, i3 & i4 Blovdovn Valves ECR-25 ICntnaent H2 Ssspie & Return Valves DCR-330 IS/6 il, i2. i3 i4 Slovdovn Valves ECR-26 ICntnaent H2 Sasple & Return Valves ICntnsent H2 Sasple !'eturn Yalves DCR-340 IS/G il, i2, i3 & i4 Blovdovn Valves ECR 27 ECR-28 ICntnaent H2 Sample & Return Valves DCR-600 IContainsent Susp to Vsste Holdup ECR-29 ICntnsent H2 Sasple & Return Valves DCR.601 IContainwent Susp to Vsste Holdup GCR-314 IHltrogen Supply to Accusulators DCR 610 lIce Condenser Drain to Drain Header ICR-5 IAccusulator Sasple Valves DCR-611 lIce Condenser Drain to Drain Header lCR-6 IAccusulator Sasple Valves OCR-620 ICntnaent Ventilation Drain to Hldup NCR-251 ISasple fros Bain Steas I.ines OCR-621 ICntnsent Ventilation Drain to Hldup NCR-252 ISasple fros Nain Steas Lines ECR-416 IContainsent I.iquid Sasplinp Systes NCR 253 ISasple fros Hain Stess Lines ECR-417 IContsinsent Liquid Sssplinp Systes NCR-254 ISasple fros Nain Steaa I.ines ECR-496 IContsinsent Liquid Sa'spling Systes HCR-105 IPrisary Systes Hot Leg Saaple ECR-497 IContainsent Liquid Sasplinp Systes HCR-106 IPrisary Systes Hot I.eg Saaple-

-ECR-535 IContainsent Gas Ssspllng Systes HCR-107 IPressurizer Liquid Sasple ECR-536 IContsinaent Gas Ssspllng Systes HCR 108 IPressurizer I.iquid Saaple OCR-919 I Cont. Des in. Cleanup Vater lsol. HCR-109 IPressurizer Stean Sssple OCR-920 I Cont. Desin. Cleanup Vster lsol. HCR-110 IPressurizer Stean Sasple OCR-300 ILetdovn Line Isolation Valve OCR-301 ILetdovn Lzne Isolation Valve KCR 252 IPrsary Nkup H20 to Prssrzer Rlf Tnk OCN- 50 IRCP Seal H20 Return Isnlation Valve OCN-350 IRCP Seal H20 Return Isolation Valve RCR. 100 IPrssrzer Rlf Tnk to Gas Analyzer RCR.IOI Iprssrzer Rlf Tnk to Gas Analyzer VCR-10 IGlycon Supply to Containsent VCR 11 IGIycon Supply to Containaent ENCLOSURE TO AEP: NRC: 07730 Page 25

ATTACHMENT NO.l TO TYPE B VARIABLES TABLE ITEM NO. B-14 CONTAINMENT ISOLATION VALVES Plant ID I Channel I

Plant ID I Channel I

YCR-20 IGlycon Return fros Contslnsent VCR-932 INfSV to Unit I G1ycon Return fros Cont a lnaent RCP CUV 4 YCR-21 VCR-922 fros CUY Unit 1 XCR-100 ICntrl Air to Cntnaent Islation Viva~ vCR-923 INCSV INfSV fros CUV Unit 1 XCR-101 ICntrl Air to Cntnaent Islatlon Vlvsl VCR-926 froa CUV Unit 2 XCR-102 ICntrl Air to Cntnaent Islation Viva VCR-927 INESV froa CUV Unit 2 XCR 103 ICntrl Air to Cntnsent Islation Viva IHCSV fros CUV Unit 3 GCR-301 I H2 Supply to Pressurizer Re 1 le f Tnk VCR-930 IXESV ICCV fr RCPs I.vr Guide Bearing Coolr VCR-931 INESV froa CUV Unit 3 CCN 451 VCR-934 IHESV froa CUV Unit 4 CCN.452 ICCV fr RCPs I.vr Guide Beartng Coolr VCR-935 IXESV froa CUY Unit 4 CCN 453 ICcv froa RCPs Thersal Barriers VCR-941 IHCSV to RCP 1 Air Cooler CCN-454 ICCV froa RCPs Theraal Barriers ICCV tO RCPS Oil COOlerc and Theraal VCR-942 IKCSV to RCP 2 Air Cooler CCN-458 vCR-943 to RCP 3 Air Cooler ICCV to RCPc Otl Coolers and Thersal IHCSV CCN.459 VCR-944 IHESV to RCP 4 Air Cooler IBarrierc VCR-945 IKESV fros RCP 1 Air Cooler ECR 31 ICOntainaent Air NOnitOr IContainaent Air Nonitor VCR-955 IHESV fros RCP 1 Air Cooler ECR 32 ECR-33 IContainsent Air Nonitor VCR-946 IKESV frOa RCP 2 Air COOler ECR-35 IContalnaent Air Nonitor VCR-956 'HESV fros RCP 2 Air Cooler ECR-.36 IContainaent Air Nonltor VCR-947 KESV froa RCP 3 Air Cooler vcR-901 IHESV to CLY Unit 1 VCR-957 HESV froa RCP 3 Air Cooler VCR 905 IHES'V to CLY Unit 2 VCR-948 HESV froa RCP 4 Air Cooler VCR-909 IHESV to CI.V Unit 3 vCR-958 HES'v froa RCP 4 Air Cooler VCR.913 IHES'V to CLV Unit 4 VCR.951 HESV to RCP 1 Air Cooler VCR-900 IHCSV to RCP CLY Unit 1 VCR-952 HESV to RCP 2 Air Cooler to RCP 3 Air Cooler VCR-904 IHESV to RCP CLV Unit 2 VCR-953 HES'v VCR-908 IHESV to RCP CI.V Unit 3 VCR-954 HCSV to RCP 4 Air Cooler VCR-960 HESV to Instrant Ra Vntilatn Units VCR-912 IHESV to RCP CLV Unit 4 Unit vCR-961 >NESV to Instrsnt Ra Vntllatn Units VCR-902 IHESV fros Cl.Y 1 froa CI.Y Unit 1 VCR-964 INESV to Instrsnt Ra Vntilatn Units VCR-903 IHESV Unit VCR-965 INESV to Instrsnt RE Vntilatn Units vcR-906 INfSV froa CLV 2 Unit VCR-962 INESV fr Instrsnt Ra Vntllatn Units VCR-907 IHESV froa CLV 2 fros CLV Unit 3 VCR-963 IHESV to Instrsnt Ra Vntilatn Units VCR-910 IHESV froa CLY Unit 3 VCR-966 INESV to Instrant Rs Vntilatn Units IHESV IXESV fr Instrant Ra Yntilatn Units VCR 911 Unit VCR-967 VCR-914 IHESV fros CLV 4 Unit CCR-440 ICCV fros Nein Steaa Penetration VCR.915 IHESV fros CLV 4 Unit 1 CCR-441 ICCV froa Nain Steaa Penetration VCR-921 IHESV to CUV VCR.925 IHCSv to CUV Untt 2 NCN-221 INain Steas to Auxiliary feed Puap vCR-929 INCSV tO CUV Unit 3 NCN-231 INain Steaa to Auxiliary feed Puap INCSV to CUV Unit 4 CCN.430 ICCV to E Pressure fqualization Fan VCR-933 RCP CUV Unit 1 CCN-431 ICCV to E Pressure Cqualization fan vCR-920 IHESV to vcR-924 INES'v to RCP CUV Unit 2 CCN-432 ICCV to v Pressure Equalization fan VCR 928 IHESV to RCP CUV Unit 3 CCN-433 ICCV to v Pressure Cquattzation fan ENCLOSURE TO AEP:NRC:07730 Page 26

ENCLOSURE TO AEP:NR~7730 ATTACHMENT NO. 2 TO TYPE B VARIABLES TABLE ITEM NO. B-14 Most of the valves listed in Attachment No. 1 to Type B Variables Item No. B-14 are located outside of containment and are only subject to an HELB outside of containment. Since they are not required to operate (per EOP's) in the event of an HELB, qualification is not required because they will be located in a mild environment should a Design Basis Event (DBE) occur where their use is required. Redundant indication is also not required because the valves are backed up by a second, redundant valve, also listed in Attachment No. 1.

Exceptions to the above are listed as follows:

DCR-301,302,303,304,310,320,330,340, and XCR-100,101,102,103 will be upgraded by replacing the position indication limit switches with environmentally ,and seismically qualified equipment. These valv'es are located outside of containment and are required to operate during an HELB.

The position indication limit switch for QCM-250 is located inside containment and is not qualified for a DBE inside of containment.

It is, however, backed up by QCM-350 which is located outside of containment and its pos'ition indication limit switch is qualified.

Should there be a DBE inside containment and QCM-250 did not indicate appropriately, QCM-350 could be used to verify isolation.

In addition an operator could be dispatched to visually verify QCM-350 closure.'f a DBE outside of containment should occur, QCM-350 is qualified for the adverse environment generated and could be backed up by QCM-250 which would not be subjected to the harsh environment and therefore, would be expected to indicate appropriately.

The position indication limit switches for VCR-11 and 21 are located inside containment and not qualified for a DBE inside containment. They are, however, backed up by VCR-10 and 20, respectively, which are located outside of containment. Should there be a DBE inside containment and VCR-11 or 21 did not indicate appropriately, VCR-10 and 20 can be used to verify isolation. In addition, an operator could be dispatched to visually verify closure. DBE's outside of containment will not create a harsh environment at VCR-10 and 20 locations.

CCM-451,452,453,454,458,459; CCM-430,431,432,433; and MCM-221,231 are qualified for an HELB.

VCR-101 thru 107 and 201 thru 207 are not listed in attachment 1 because their function is specifically listed in the Type D Variables Table, Item D-31.

.w ENCLOSURE TO AEP:Nl7730 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 requirement's.

(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.

adverse containment conditions 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 adverse containment conditions are 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) Per SER issued June 16, 1981 concerning Auxiliary Feedwater System reliability, it is only required that qualifie-, S/G narrow range level indication be provided and backed up by qualified Auxiliary Feedwater Flow Indication. S/G wide range level indication is not required to be environmentally qualified or powered from a Class IE power source.

(j) Containment Sump Water Temperature will give none of the 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.'

1

~ . ~

'NCLOSURE TO- AEP:N 7730 (k) DELETED (l) INTENTIONALLY LEFT BLANK flow from qualified (m) Redundancy is accomplished by verifying pump instrumentation.

(n) DELETED (o) INTENTIONALLY LEFT BLANK (p) Range is adequate to safely monitor operation.

(q) Not required per NUREG 0737 II.B.3 (r) These valves are left normally open (safe position), the breakers racked out and they cannot change position. Therefore, Environmental Qualification of position indication is not required.

(s) Redundancy can be provided by VCR-101 thru 107 which are located inside containment. VCR-201 thru 207 are located outside containment.