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

\\

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

~ 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 The implementation schedule provided for each variable is the current best estimate 'f 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 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 does not, nor is it 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 operator to take specific manually controlled actions for which no automatic control is provided 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 sre 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 KOP'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 No.

Purpose Variable Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-1 U-2 Q

Q h

F S

Location Schedule Schedule A-1 Maintain Pressur-Centrifigal IFI-51,52, 0-200 CPM izer Level during Chg Pump Flow 53,54 S/C Tube rupture IE Control Room Qualify or replace control 1987 're-Panel SIS room indicators with fueling seismically qualified outage equipment 1987 re-fueling outage A-2 Manual Trip of RC RCS Pressure NPS-121,122 0-3000psig Pumps based on RCS (wide range) pressure Y

Y Y

Y IE Control Room Qualify or replace control 1987 re-1987 re-Panel RHR room recorder with fueling fueling seismically qualified outage outage equipment h-3h-4'OT USED NOT USED A-5 h-6 NOT USED NOT USED h-7 Determination of required core exit temperature by S/C Pressure S/C Pressure MPP-210,211.

0-1200psig 212,220, 221,222, 230,231

'32,240, 241.242 Y

Y Y

Y IE Control Room Qualify or replace control 1987 re-1987 re-Panel SC room indicators with fueling fueling seismically qualfied outage outage equipment ENCLOSURE TO AEPINRC:07730 Page 7

Item No.

Purpose Variable Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-l U-2 A

P S

Location Schedule Schedule A-8 Determination of adverse containment Containment Sump Level NLA-310 NLI-311,320>

321 589.5 to Y

614 ft. el-evation (bottom of sump to max flood level)

Y Y

Y IE Control Room Qualify or replace control Panel RHR room indicators vith seismically qualified equipment 1987 re-1987 re-fueling fueling outage outage h-9 Hanual Reduction of S/C Level ECCS Plov Nerrrov range (Secondary heat sink capability)

BLP-110,111>

112,120, 121.122>

130,131, 132,140.

141>142 From belov Y

1st stage separator to 2nd stage separator Y

Y Y

IE Control Room Panel SC Qualify or replace control room indicators and/or recorders vith seismic-ally qualified equipment 1987 re-fueling outage 1987 re-fueling outage A-10 Manual Reduction of ECCS Flov h-11 Pressuriaer Level NLP-151,152>

0-100X Y

153 (96X of Total Volume)

NOT USED Y

Y Y

IE Control Room Panel PZR (NLP-151 also HSD)

Qualify or replace control room indicators and/or, recorders vith seis-mically qualified equipment 1987 re-fueling outage 1987 re-fueling outage h-12 Determination of adverse containment Containment brea Radiation Honitor High Range VRA-1310,

1410, (Unit 1)

2310, 2410 (Unit 2) 1 R/)R to lxlo R/HR Y

NA Y

Y IE Control Room See footnote (c)

Panel RHS Nh NA A-13 Manually establish or trip containment spray h-14 Containment Pressure (Narrov range)

PPP-300,301, 302,303

-5 to +12 psig NOT USED NA Y

Y Y

IE Control Room Qualify or replace Panel SPY indicators vith seismically qualified equipment See footnote (d) 1987 re-1987 re-fueling fueling outage outage ENCLOSURE TO AEPINRC:07730 Page 8

Item No.

Purpose Variable Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd IJ-1 U-2 Q

h F

S Location Schedule Schedule A-15 Manual Reduction of Auxiliary FFI-210,220, ECCS Flow Peedwater Flow 230,240 (Secondary heat sink capability) 0-250 KPPH Y

Y Y

Y IE Control Room Panel SC Redundancy provided by diverse variable - S/C narrow range level which is qualified.

Qualify or replace indicators, power

supplies, and square root converters with seismical qualified equipment.

Powe from IE source.

lyr 1987 re-1987 re-fueling

fueling, outage outage A-16 Manual Transfer to RUST Level cold leg recircula-tion in low level in RUST ILS-950,951 essentially NA Y

Top 'to Bottom (IOOZ of Total Volume)

Y IE Control Room Panel SPY Qualify or replace indicators and/or recorders with seismic-ally qualified equipment.

Also see footnote (d) 1987 re-1987 re-fueling fueling outage outage A-17 A-18 A-19 A-20 h-21 h-22 h-23 h-24 Manual Trip or re-duction of Press-urirer Spray and ECCS Flow Degrees Sub-cooling Nh NOT USED 0-199'F sub-Y Nh cooling 0-199'F Superheat NOT USED NOT USED NOT USED NOT USED NOT USED NOT USED Y

Nh IE Control Room See footnotes (b) 6 (c)

Panel BA which apply beyond the isolating devices NA NA A-25 Manual Reduction of ECCS Flow Core Exit T/C's T/C 1-65 200-2300 F

Y Y

Y IE Control Room Panel FI (IJ-1) Panel RMS (U-2)

All required cables.

connectors, indicators, signal processing equipment to be replaced with qualified equipment (Unit 2 only. No action required Unit 1)

NA See foot-note (g)

ENCLOSURE TO AEP:NRC:07730 Page 9

Item No.

Purpose Variable Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-l U-2 A

F S

Location Schedule Schedule h-26 A-27 h-28 Manual trip of CCP Breaker RCP's Status Pump IE,IW NOT USED NOT USED OPEN/CLOSE Nh Y

Y Y

IE Control Room Qualify or replace Panel Bh control room indicators with seismically qualified equipment See footnotes (d)

& (m)

End of End of 1988 1988 A-29 Manual trip of RCP's SI Pump Breaker Status Pump 1N,IS OPEN/CLOSE NA Y

Y Y

IE Control Room Qualify or replace Panel SIS control room indicators with seismically qualified equipment See footnotes (d)

& (m)

End of 1988 End of 1988 A-30 h-31 h-32 h-33 h-34 A-35 Manual Trip of RCP's Identify Ruptured Stcam Generator Safety In]ec-IFI-260.266 cion Pump Flow S/0 Blowdown DRA-300,353 Radiation NOT USED NOT USED NOT USED NOT USED 0-800CPM 10-10E06 CPM Nh Y

Y Y

Nh Y

Y Y

IE Control Room Qualify or replace Panel SIS control room indicators with seismically qualified equipment.

See footnote (d)

IE Control Room Qualify or replace all Panel RMS components with seismic-ally qualified equipment and power from IE source.

See footnote (d) 1987 re-fueling outage 1988 re-fueling outage 1987 re-fueling outage 1989 re-fueling outage A-36 A-37 NOT USED NOT USED

~ 'I ENCLOSURE TO AEP:NRCI07730 Page 10

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 No.

Variable Cat.

Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-l 0-2 A

F S

Location Schedule Schedule B-1 Reactivity Control Neutron Flux 1

NE-41A,41'2A,42B.

43A,438, 44A,448 0-1202 full power NA Y

Y Y

IE Control Room None Required Panel NIS See footnote (f)

NA NA B-2 Control Rod Position 3

CA1-8 I CB1-4 CC1-8, CDI-9 SA1-8, 5B1-8 Full in or NA Nh NA Nh NA Control Room None required not full in Panel RC NA NA B-3 RCS Soluble Boron Con-centrate 3

NSX-101,103 Nh NA NA Nh NA NA See Item C-2 and footnote (a)

NA B-4 RCS Cold Leg Temp-erature 1

NTR-210,220, 230,240 0-700 F

Y Y

Y Y

IE Control Room Qualify or replace Panel DTU recorders with seismic-ally qualified equipment 1987 re-fueling outage 1987 re-fueling outage B-5 Core Cooling RCS Hot Leg Mater Temperature 1

NTR-110,120, 0-700'F 130.140 Y

Y Y

Y IE Control Room Qualify or replace record-1987 rc-Panel DTU ers with seismically fueling qualified equipment outage 1987 re-fueling outage B-6 RCS Cold 1

Leg Mater Temperature Sce item B-4 B-7 B-8 RCS Pressure Core Exit Temperature Sce item A-2 See item h-25 ENCLOSURE TO AEP:NRC107730 Page 11

Item Purpose No.

Variable Cat.

Tag Nos.

Range E

S Q

S P

Display' F

S Location Remarks/Action Req'd U-1 U-2 Schedule Schedule B-9 8-10 Coolant Inventory Degrees of Subcooling NLI-110,111 Top of head 120,121, vent piping 130,131 to bottom of vessel (1002 of Volume)

Y Y

Y Y

IE Control Room None required Panel SIS See item h-17 NA NA B-ll Maintaining RCS Pressure RCS Integrity See item h-2 B-12 Containment Sump Water Level See item A-8 B-13 Containment Pressure (Wide Range) 1 PPA-310,312

-5 to 36psig NA Y

Y Y

IE Control Room Panel SPY Qualify or replace Indicators/recorders, vith seismically qualified equipment.

Also see item h-13 for narrov range Sec footnote (d) 1987 re-1987 re-fueling fueling outage outage B-IA Maintaining Containment Integrity Containment Isolation Valve Posi-tion (ex-cluding check valves) 1 See listing CLOSED -

Y Y

Y in Attach-NOT CLOSED ment 1 to these tables Y

IE Control Room Panels IV, BA,SIS,SPY Replace Limit svitches vith env 6 seismically qualified devices as noted in Attachments 1

6 2 to these tables.

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

1988 re-fueling outage 1989 re-fueling outage 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 No.

Variable Cat.

Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-l U-2 Q

Q A

P S

Location Schedule Schedule C-1 Puel Cladding Core Eric Temperature See item A-25 C-2 Radioactive concentra-tion or Radiation Level in Circulating Primary Coolant 1

NSX-101,103 NA Y

Y Y

Y Y

NA m

See footnote (h) 1987 re-1987 re-Replace solenoid valves refueling refueling with seismically and outage outage environmentally qualified equipment C-3 Analysis of Primary Coolant (Gamma Spectrum)

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

Boundary See item A-2 C-5 Containment Pressure See items A-13 and 8-13 C-6 Containment Sump Water Level See item A-8 C-7 Containment Area Radi-ation See item A-12 ENCLOSURE TO AEPiNRC:07730 Page 13

item No.

Purpose Variable Cat.

Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-l U-2 Q

Q A

P S

Location Schedule Schedule C-g Effluent Radioactiv-ity-Noble gas Effluent from Con-denser Air Removal Sys-tem Exhaust 3

SRA-1900 IOE-07 to (Unit I IOE03 SRA-2900 p.Ci/cc (Unit 2)

NA NA NA NA NA Control Room No accion required CT-I Control Terminal NA C-9 Containment C-IO RCS Pressure Containment Hydrogen Concentra-tion ESR-I thru 9 NA NA Y

Y Y

IE NA Sce item h-2 See footnote (d)

No action required NA NA C-lI Containment Pressure See items A-13 and B-I3 C-12 Containment Effluent Radioactiv-ity-Noble gases from identified release points ERS-1300 'OE-07 to 1400(Unit IOE05 I)

/ICi/cc ERS-2300, 2400 (Unit 2)

NA NA NA NA NA Panel WDG See footnote (d)

No Action Required NA NA ENCLOSURE TO AEP:NRC:07730 Page 14

Item No.

Purpose Variable Cat.

Tag Nos.

Range E

S Q

S F

Display Remarks/Action Req'd U-I U-2 Q

Q A

F S

Location Schedule Schedule C-13 Effluenc 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 SEE ITEN C-12

~

~

ENCLOSURE TO AEP:NRC107730 Page 15

Type D Variables:

"those variables that provide information to indicate the operation of individual safety systems and safety.

These variables are to help the operator make appropriate decisions in using the individual mitigating the the consequences of an accident."

Note:

The schedule and status for each instrument ments of Regulatory Guide 1.97, Rev 3 will be met.

other systems important to systems important to safety in is for when all of the require-Item Purpose No.

Variable Cat.

Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-I U-2 Q

Q A

F S

Location Schedule Schedule D-I RHR System IU1R System Flow 2

IPI-310,311, 0-1500 CPH 320,321 0-5500 CPH Y

NA Y

Nh Nh Control Room No Action Required Panel RHR NA D-2 RHR Heat Ex-2 ITR-311,321 50-400 F

change Out-let Temp Y

NA Y

NA Nh Control Room Replace RTD's with Panel RHR env. qualified equip-ment.

See footnote (p) 1987 re-1987 re-fueling fueling outage outage D-3a SI Systems Accumulator Tank Level 2

ILA-IIO-,III 120,121, 130,131, 140,141 0-133" wc (wide range)

(522 of Total Volume) 105.8 to

-121.7 in.

(narrow range)

(7.5X of Total Volume)

Y NA Y

Nh NA Control Room Replace one wide range Panel SIS transmitter with env.

qualified equipment.

See footnote (p) 1988 re-1989 re-fueling fueling outage outage D-3b Accumulator Tank Pres'-

sure 2

IPA-110.111, 0-800 psig Y

NA Y

120,121, 130,131.

140,141 NA NA Control Room Replace one transmitter/

Panel SIS tank with env. qualified equipment 1988 re-1989 re-fueling fueling outage outage D-4 Accumulator Tank Isola-tion Valve Position 2

IM0-110,120, Closed or NA NA Y

130,140 Open NA NA Control Room None Required Panel SIS See footnote (r) 1987 re-1987 re-fueling fueling outage outage ENCLOSURE TO AEP:NRC:07730 Page 16

Item Purpose No.

Variable Cat.

Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-l U-2 Q

Q A

F S

Location Schedule Schedule D-5 Boric Acid Charging Flov See item D-24 D-6 D-7 D-8 Flov in HPI System Flov in LPI System RWST Level See item h-1 See item D-1 See item A-16 D-10 Primary Sys-tem Safety Relief Valve Positions or Flov Thru or pressure in Relief Valve Lines 2

QR-107 A,BE C,D D-9 Primary Cool-RCP Status 3

QI,Q2.Q3,Q4 anc System 0-1200A Nh NA NA NA NA NA Control Room No Action Required Panel RCP Y

NA Y

NA NA Concrol Room See footnote (b)

P~nel RC No hccion Required NA NA NA NA D-11 D-12 Pressurizer Level Pressurizer Heater Sca-tus 2

Croup AI,A2, A3,C1,C2,C3 See item h-10 ON/OFF NA NA Y

Nh NA Control Room See footnote (d)

Panel PZR No Action Required NA NA D-13 Qu5nch Tank Level 3

NLA-351 Essencially NA NA Top to Bottom (74Z of Total Volume)

NA NA NA Control Room None required Panel PZR Sce footnote (p)

NA NA D-14 Quench Tank Temperature 3

NTA-351 50-750'F NA NA NA NA NA Control Room Panel PRZ Increase Range from 50'F g )Q;$ to required 1987 re-1987 re-fueling fueling outage oucage ENCLOSURE TO AEP:NRCI07730 Page 17

Item No.

Purpose Variable Cat.

Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-l U-2 Q

Q A

F S

Location Schedule Schedule D-14 a Quench Tank Pressure 3.

NPA-351

-10 to 100 NA psig NA Nh NA NA Control Room None Required Panel PRE NA NA D-15 Secondary Sys-S/0 Level tern (Steam Generator) 1 BLI-110'20>

130>140 (vide range)

From 12" NA above cube sheec to sep-arators NA Y

Y NA Control Room None required See Panel SG footnote (i)

NA D-1&a D-16b D-17 Safety/Re-lief Valve Positions Main Steam Flow Mein Feed-water Flow 2

MFC-110,111, 120,121, 130,131, 140,141 3

FFC-210,211

'20,221, 230,231, 240 F 241 See Item D-16b for alternate instrumentation 0-4x10 PPH Y

NA Y

NA NA Control Room Hone required 6

Panel SC 0-Sx10 PPH NA NA NA NA NA Control Room None required 6

Panel BA NA NA NA D-18 Auxiliary Feed-Aux Feed-vacer System vater Flow See item h-15 D-19 Condensate Scorage Tank Level 1

CLI-113 CLR-110>

111 Essentially Top to Bot-tom (952 Total Volume)

NA Y

Y Y

IE Control Panel Qualify or replace 1987 re-1987 re-instruments vith seismic-fueling fueling ally qualified equipment.

outage outage See footnotes (d)

(p) (2 channels only)

I D-20 Containment Cooling System Containment Spray Flov 2

IFI-,330.331 (Upper con-tainment) 0-200CPM NA NA Y

NA NA Control Room No hccion Required Panel SPY See footnotes (d)

& (e)

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

Item Purpose No.

Variable Cat.

Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd Q

Q h

F S

Location U-l U-2 Schedule Schedule D-22 Containment Atmosphere Temperature 2

ETR-11,12,13, 0 to 14,15 '6, 400 F 17,18,19, 20,21,22, 23,24,25, 26,27 Y

Nh Y

NA Nh Control Room Replace six (6) tech spec 1988 re-1989 re-Panel h-14 related RTD's with envi-fueling fueling ronmentally qualified outage outage equipment.

Increase range from 0 to 300 F to as specified.

D-23 Containment 2

Sump 'Mater Temperature No Action Required See footnote (j)

D-24 Chemical and Make up 2

QFI-200 0-200 GPM NA NA Y

NA NA Control Room No Action Required See NA Volume Control Flow-In Panel BA footnote (d)

System NA D-25 D-26 Letdown Flow Out Volume Con-trol Tank Level 2

QFI-301 2

QLC-451,452 0-200 GPM Essential-ly top to bottom (65X of Total Volume)

NA NA Y

NA NA Control Room No Action Required, Panel BA and See footnote (d)

HSD Nh NA Y

NA NA Control Room No Action Required Panel BA See footnote (d)

& (p)

NA NA NA NA D-27 Cooling Hater System CCM water Temperature to ESF Sys-tem 2

CTR-410.415.

0-200 F

420,425 Nh NA Y

Nh NA Control Room No Action Required Panel ESN See footnote (d)

NA NA D-28 CCM Flow to ESF System 2

CFI-410,419, 0-10000GPM 420,429 0-6000GPM Nh NA Y

Nh Nh Control Room No Action Required Panel CCN See footnote (d)

Nh Nh D-29 Radwaste Systems High Level Radioactive Liquid Tank Level 3

RLS-255 '56 Essentially Top to Bot-tom (84X of Total Volume)

Nh NA NA Nh NA Panel NDG None required NA See footnote (p)

ENCLOSURE TO AEP:NRC:07730 Page 19

Item No.

Purpose Variable Cat.

Tag Nos.

Range E

S g

S P

Display Remarks/Action Req'd U-l U-2 A

F S

Location Schedule Schedule D-30 Radioactive Cas Holdup Tank Pres-sure 3

RPC-310,320, 330,340, 350,360, 370,380 0-225 psig Nh Hh Nh Nh NA Panel QDC Increase range from 0-150 psig to 0-225 psig As specified 1987 re-1987 re-fueling fueling outage outage D-31 Ventilation System Emergency Ventilation Damper Pos-ition 2

VCR-201 thru Open-Closed Y

NA 207 Y

Nh Nh Control Room Panel IV VCR-207 on Control Room Panel SPY Replace Limit Switches VCR-201 6 202 with env.

qualified equipment.

Footnote (d) applies to VCR-203 thru 207.

See footnote (s) 1988 re-1989 re-fueling fueling outage Power Supplies Status of Standby Power. and other Energy Sources Im-portant to Safety D-32a Diesel Cen Status 2

DCIAB DC1CD 0-800A Nh Nh Y

Nh HA Control Room See footnote (d)

Panel Sh No Action Required NA NA D-32b 4kv Safety Related Po-wer Systems Status 2

Bus Tllh.

T11B, T11C, T11D 0-150V Nh NA Y

Nh Nh Control Room See footnote (d)

Panel SA No Action Required Nh Nh D-32c 250V Battery 2

Battery AB Power System Battery CD Status 0-300V NA NA Y

NA NA Control Room See footnote (d)

Panel SA No Action Required NA NA D-32d 120VAC Safe-2 Channel I,II, 0-150V ty Related III, IV Power System Status NA NA Y

NA NA Control Room See footnote (d)

Panel SA No Action Required NA D-32e Instrument Air Status 2,XP I-100 XPI-50 XPI-20 XPI-85 0-150psig 0-100psig 0-60psig 0-160psig Nh Nh Y

NA NA Control Room These are mechanical NA Panel SV devices no electrical components No Action Required NA 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 I

No.

Variable Cat.

Tag Nos.

Range E

S g

S P

Display Remarks/Action Req'd U-l U-2 A

F S

Location Schedule Schedule E-1 Containment Radiation Containment Area Radia-tion High Range See item A-12 E-2 Area Radiation Radiation Exposure Rate (in-side build-ings or

~here areas of access are required to service equipment important to safety) 3 VRC-301 NRA-340 RRA-322 IOE-01 to NA 10E04 mR/hr NA NA'A NA Control Room None required Panel RHS See footnote (p)

NA E-3a Noble Cases and vent. Flow Rate Containment or Purge Effluent SEE ITEH E-3e E-3b Reactor Shield Building

Annulus, SEE ITEN E-3e E-3c Aux Building 2

SEE ITEH E-3e E-3d Condenser Air Removal System Ex-haust 2

SFR-1900 (Unit 1)

SFR-2900 (Unit 2)

SFR-401 10E-06 to 10E03

+Ci/cc 0-2000 scfm NA NA Y

NA NA See footnotes (d) 4 (P)

NA ENCLOSURE TO AEP I NRC107730 Page 21

Item Purpose No.

Variable Cat.

Tag Nos.

Range E

S Q

S P

Display Remarks/Action Req'd U-l.-

U-2 A

F S

Location Schedule Schedule E-3e Common 2

Plant Vent VRS-1500 (Unit 1)

VRS-2500 (Unit 2)

VRF-315 10E-07 to 10E05 pCi/cc 0-200K scfm NA NA Y

Nh Nh Control Room None Required CT-1 Control See footnote (d)

Terminal NA NA E-3f E-3g Vent from 2

S/C Safety Relief Valves Other ident-2 ified re-lease points HRA-1600 1700 (Unit 1)

HRA-2600 2700 (Unit 2)

SRA-1800'Unit 1)

SRA-2800 (Unit 2)

SFR-201 3 to 20E05 p,Ci/cc 108-07 to 10E03 plCI/cc 0-1000 scfm Y

Nh Y

NA Nh Control Room None Required Panel RHS Nh NA Y

NA NA Control Room None Required Panel FI See footnote (d)

NA NA NA E-4 Particulates and Balogens All identi-3 fied release points (ex-cept S/C Safety Re-lief valves and Conden-ser air'e-moval System exhaust)

Sampling and onsite analysis See Item E-3e Environ Radia-tion and Radio-activity Airborne Radioacti-vity and Particulates sampling and analysis (portable)'

Nh 10-9 to NA NA NA NA NA NA 10-3 P Ci/cc (minimum)

None Required Nh ENCLOSURE TO AEPINRC:07730 Page 22

Iten Ho+

Purpose Variable Cat.

Tag Nos.

Range E

S Q

S P

Display A i S

Location Renarks/Action Req'd U-l 0-2 Schedule Schedule E-5b Plant and Environs Radiation (Portable) 3 Nh 10E-3 to Nh Nh Nh Hh Nh NA 10E4 R/HR (ninimun)

None required Nh NA I

E-Sc I

Plant and Environs Radioacti-vity (Port-able) 3 Nh NA NA Nh Nh HA Nh Nh None required Nh NA E-6 Meteorology Wind Direc-cion 3

EFR-410,411, 0-360 420,421 NA NA Nh Hh Nh Control Roon None required Panel Fix Nh NA E-7 E-S E-9a E-9b Accident Sanp-ling Prinary Coolant and Suep

'Wind Speed Estination of htnos-pheric Stability Cross Acti<<

vicy Canna Spec-trun 3

EPR-400,401, 0-100 nph NA NA 402,403 3

ETR-400,401,

-35 to 50'C Nh NA ETQ-401,402 403,404 SEE ITEM C-2 SEE ITEM C-3 NA Nh Nh Control Roon None required Panel Plx NA NA NA Control Roon None required Panel Fix Nh NA Nh E-9c Boron Con-tent SEE ITEM B-3 E-9d E-9f Chloride 3

HSX-101.103 HA Content Dissolved 3

NSX-101,103 0-2000 cc/

H2 or total kg gas HA HA NA HA NA HA Nh Nh NA NA Nh Nh SEE ITEM C-2 SEE ITEM C-2 Nh NA NA ENCLOSVRE TO AEP:NRC:07730 Page 23

O.

Item Purpose Variable Cat.

Tag Nos.

Ho+

Range E

S Q

S P

Display h

F S

Location Remarks/Action Req'd U-l U-2 Schedule Schedule E-9g Bissolved 3

NSX-101, 0-20 ppm NA Nh Nh Nh Hh NA 2

103 SEE ITEM C-2 NA Nh E-9h pH 3

NSX-101'.0 to 8.0 Nh NA NA HA NA Nh 103 pH SEE ITEM C-2 Nh NA E-10a Containment Air H

Content 3

ESX-001 2

Nh NA Nh NA NA Nh NA None required NA NA E-10b 02 Content 3

HA NA Nh Nh HA HA NA NA Hone required See footnote (q)

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

ATTACHHENT NO.l TO TYPE B VARIABLES TABLE ITEH NO.

B-14 CONTAINHENT ISOLATION VALVES Plant ID CCR-455 CCR-456 CCR-457 CCR-460 CCR-462 DCR-201 DCR.204 DCR-205 DCR-206 DCR-207 DCR-301 OCR-302 DCR-303 DCR 304 DCR-310 DCR-320 DCR-330 DCR-340 DCR-600 DCR.601 DCR 610 DCR-611 OCR-620 OCR-621 ECR-416 ECR-417 ECR-496 ECR-497

-ECR-535 ECR-536 OCR-919 OCR-920 Channel I

I ICCV to Reactor Supports ICCV froa Reactor Supports ICCV frOs ReaCtOr SuppOrto ICCV fros Excess Letdovn Hx ICCV to Excess Letdovn Hx IRC Drain Tink to Vent Header IRC Drain Tank to Gas Analyzer IRC Drain Tank Suction Isolation IRC Drain Tank Suction isolation IHitrogen Supply to RC Drain Tank IS/G Slovdovn Saaple Isolation IS/G Blovdovn Saaple Isolation IS/6 Blovdovn Sasple isolation IS/G Slovdovn Sasple Isolation IS/G il, i2, i3 & i4 Blovdovn Valves IS/G il, i2, i3

& i4 Blovdovn Valves IS/6 il, i2. i3

& i4 Slovdovn Valves IS/G il, i2, i3

& i4 Blovdovn Valves IContainsent Susp to Vsste Holdup IContainwent Susp to Vsste Holdup lIce Condenser Drain to Drain Header lIce Condenser Drain to Drain Header ICntnaent Ventilation Drain to Hldup ICntnsent Ventilation Drain to Hldup IContainsent I.iquid Sasplinp Systes IContsinsent Liquid Sssplinp Systes IContsinsent Liquid Sa'spling Systes IContainsent Liquid Sasplinp Systes IContainsent Gas Ssspllng Systes IContsinaent Gas Ssspllng Systes ICont.

Des in. Cleanup Vater lsol.

ICont.

Desin.

Cleanup Vster lsol.

Plant ID ECR-10 ECR. 11 ECR-12 ECR-13 ECR-14 ECR-15

'CR-16 ECR-17 ECR-18 ECR-19 ECR-20 ECR-21 ECR-22 ECR-24 ECR-23 ECR-25 ECR-26 ECR 27 ECR-28 ECR-29 GCR-314 ICR-5 lCR-6 NCR-251 NCR-252 NCR 253 NCR-254 HCR-105 HCR-106 HCR-107 HCR 108 HCR-109 HCR-110 OCR-300 OCR-301 KCR 252 OCN-50 OCN-350 RCR. 100 RCR.IOI VCR-10 VCR 11 Channel I

I ICntnsent.

H2 Sssple

& Return Valves ICntnsvnt 82 Saaple

& Return Valves ICntnsent H2 Sasple

& Return Valves ICntnsent H2 Sasple

& Return Valves ICntnsent H2 Sasple

& Return Valves ICntnsent H2 Sasple

& Return Valves ICntnsent H2 Sasple

& Return Valves ICntnsent H2 Saaple

& Return Valves ICntneent H2 Sasple

& Return Valves ICntnaent H2 Sssple

& Return Valves ICntnsent H2 Saaple

& Return Valves ICntnsent H2 Sssple

& Return Valves ICntnaent H2 Sasple

& Return Valves ICntnsent H2 Sasple

& Return Valves ICntnsent H2 Sasple

& Return Valves ICntnaent H2 Ssspie

& Return Valves ICntnaent H2 Sasple

& Return Valves ICntnsent H2 Sasple !'eturn Yalves ICntnaent H2 Sample

& Return Valves ICntnsent H2 Sasple

& Return Valves IHltrogen Supply to Accusulators IAccusulator Sasple Valves IAccusulator Sasple Valves ISasple fros Bain Steas I.ines ISasple fros Nain Steas Lines ISasple fros Hain Stess Lines ISasple fros Nain Steaa I.ines IPrisary Systes Hot Leg Saaple IPrisary Systes Hot I.eg Saaple-IPressurizer Liquid Sasple IPressurizer I.iquid Saaple IPressurizer Stean Sssple IPressurizer Stean Sasple ILetdovn Line Isolation Valve ILetdovn Lzne Isolation Valve IPrsary Nkup H20 to Prssrzer Rlf Tnk IRCP Seal H20 Return Isnlation Valve IRCP Seal H20 Return Isolation Valve IPrssrzer Rlf Tnk to Gas Analyzer Iprssrzer Rlf Tnk to Gas Analyzer IGlycon Supply to Containsent 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 YCR-20 YCR-21 XCR-100 XCR-101 XCR-102 XCR 103 GCR-301 CCN 451 CCN.452 CCN 453 CCN-454 CCN-458 CCN.459 ECR 31 ECR 32 ECR-33 ECR-35 ECR-.36 vcR-901 VCR 905 VCR-909 VCR.913 VCR-900 VCR-904 VCR-908 VCR-912 VCR-902 VCR-903 vcR-906 VCR-907 VCR-910 VCR 911 VCR-914 VCR.915 VCR-921 VCR.925 vCR-929 VCR-933 vCR-920 vcR-924 VCR 928 I

Channel I

IGlycon Return fros Contslnsent I G1ycon Return fros Cont a lnaent ICntrl Air to Cntnaent Islation Viva~

ICntrl Air to Cntnaent Islatlon Vlvsl ICntrl Air to Cntnaent Islation Viva ICntrl Air to Cntnsent Islation Viva I H2 Supply to Pressurizer Re 1 lef Tnk ICCV fr RCPs I.vr Guide Bearing Coolr ICCV fr RCPs I.vr Guide Beartng Coolr ICcv froa RCPs Thersal Barriers ICCV froa RCPs Theraal Barriers ICCV tO RCPS Oil COOlerc and Theraal ICCV to RCPc Otl Coolers and Thersal IBarrierc ICOntainaent Air NOnitOr IContainaent Air Nonitor IContainsent Air Nonitor IContalnaent Air Nonitor IContainaent Air Nonltor IHESV to CLY Unit 1

IHES'V to CLY Unit 2 IHESV to CI.V Unit 3 IHES'V to CLV Unit 4

, IHCSV to RCP CLY Unit 1

IHESV to RCP CLV Unit 2 IHESV to RCP CI.V Unit 3 IHESV to RCP CLV Unit 4 IHESV fros Cl.Y Unit 1

IHESV froa CI.Y Unit 1

INfSV froa CLV Unit 2 IHESV froa CLV Unit 2 IHESV fros CLV Unit 3 IHESV froa CLY Unit 3 IHESV fros CLV Unit 4 IHESV fros CLV Unit 4

IHESV to CUV Unit 1

IHCSv to CUV Untt 2 INCSV tO CUV Unit 3 INCSV to CUV Unit 4

IHESV to RCP CUV Unit 1

INES'v to RCP CUV Unit 2 IHESV to RCP CUV Unit 3 Plant ID Channel VCR-932 VCR-922 vCR-923 VCR-926 VCR-927 VCR-930 VCR-931 VCR-934 VCR-935 VCR-941 VCR-942 vCR-943 VCR-944 VCR-945 VCR-955 VCR-946 VCR-956 VCR-947 VCR-957 VCR-948 vCR-958 VCR.951 VCR-952 VCR-953 VCR-954 VCR-960 vCR-961 VCR-964 VCR-965 VCR-962 VCR-963 VCR-966 VCR-967 CCR-440 CCR-441 NCN-221 NCN-231 CCN.430 CCN-431 CCN-432 CCN-433 I

I INfSV to RCP CUV Unit 4

INCSV fros CUY Unit 1

INfSV fros CUV Unit 1

INESV froa CUV Unit 2 IHCSV froa CUV Unit 2 IXESV fros CUV Unit 3 INESV froa CUV Unit 3 IHESV froa CUV Unit 4

IXESV froa CUY Unit 4

IHCSV to RCP 1 Air Cooler IKCSV to RCP 2 Air Cooler IHCSV to RCP 3 Air Cooler IHESV to RCP 4 Air Cooler IKESV fros RCP 1 Air Cooler IHESV fros RCP 1 Air Cooler IKESV frOa RCP 2 Air COOler

'HESV fros RCP 2 Air Cooler KESV froa RCP 3 Air Cooler HESV froa RCP 3 Air Cooler HESV froa RCP 4 Air Cooler HES'v froa RCP 4 Air Cooler HESV to RCP 1 Air Cooler HESV to RCP 2 Air Cooler HES'v to RCP 3 Air Cooler HCSV to RCP 4 Air Cooler HESV to Instrant Ra Vntilatn Units

>NESV to Instrsnt Ra Vntllatn Units INESV to Instrsnt Ra Vntilatn Units INESV to Instrsnt RE Vntilatn Units INESV fr Instrsnt Ra Vntllatn Units IHESV to Instrsnt Ra Vntilatn Units INESV to Instrant Rs Vntilatn Units IXESV fr Instrant Ra Yntilatn Units ICCV fros Nein Steaa Penetration ICCV froa Nain Steaa Penetration INain Steas to Auxiliary feed Puap INain Steaa to Auxiliary feed Puap ICCV to E Pressure fqualization Fan ICCV to E Pressure Cqualization fan ICCV to v Pressure Equalization fan 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)

INTENTIONALLYLEFT BLANK (m)

Redundancy is accomplished by verifying pump flow from qualified instrumentation.

(n)

DELETED (o)

INTENTIONALLYLEFT 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.