ML17255A663

Forwards Rept Comparing Instrumentation Listed in Rev 2 to Reg Guide 1.97 & Instrumentation Available at Facility. Revised Emergency Procedures,Developed to Meet Suppl 1 to NUREG-0737 Requirements,Expected to Be Complete by Aug 1984

ML17255A663
Person / Time
Site:	Ginna
Issue date:	01/31/1984
From:	Maier J ROCHESTER GAS & ELECTRIC CORP.
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8402070380
Download: ML17255A663 (17)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDE)

ACCESSION NBR:8002070300 ODOC,DATE: 80/OI/31 NOTARED:

NO DOCKET,S FACIL,:50 244 Rober t Emmet-Ginna Nuclear Pl ant F

Uni,,t 1F Rochester G

05000244 AUTH BYNAME AUTHOR AFFILIATION MAIERgJ ~ E ~

Rochester Gas L Electric Corp.

REC IP ~ NAME.

RECIPIENT AFFILIATION C R tjTCHFIEL&g D ~

Oper ating Reactor s Branch 5

SUBJECT:

For wards.rept comparing. instrumentation listed in Rev-2 to Reg Guide 1,97 8 instrumentation available at facility.

Revised emergency proceduresidevelope to meet Suppl 1-to N~REG"0737 requirements~expected to be complete by Aug 1984

'ISTRIBUTION CODE! A003S,COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR(Licensing Submittal:

Suppl 1 to NUREG-0737(Generic Ltr'82 33)

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Ill/Ill/ill ROCHESTER GAS AND ELECTRIC CORPORATION

~ 89 EAST AVENUE, ROCHESTER, N.Y. I 4649

~JOHN E. MAICR Vice President TCI.CPHONE AREA coDE Vie 546-2700 January 31, 1984 Director of Nuclear Reactor Regulation Attention:

Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.

5 U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Subject:

NUREG 0737, Supplement 1

R.

E. Ginna Nuclear Power Plant Docket No. 50-244 I

I l

A

Dear Mr. Crutchfield:

Letters dated April 15, 1983 and August 3, 1983 provided RGGE's planned schedule for meeting the requirements of Supplement 1 to NUREG-0737.

RGaE committed to submit a Regulatory Guide 1.97 compliance report.in January 1984.

The attachment to this letter is that report and provides a comparison between the instrumenta-tion listed in the Regulatory Guide and the instrumention avail-able at Ginna.

The attached comparison is meant to describe the instrumentation installed at Ginna.

It is not necessarily meant to be a listing of the instrumentation that RGGE believes is required for response to emergency situations.

The basis for requiring certain instruments or for deviating from the guidance of Regulatory Guide 1.97 will be developed, at least in part, around those parameters used in revised emergency procedures.

The revised procedures are also being developed to meet the require-ments of Supplement 1 to NUREG-0737, and a first draft is scheduled to be completed in August of this year.

Accordingly, justification of instrumentation to be provided for preventing and mitigating accidents and a schedule for modifications to the plant, if required, will be provided in February 1985.

Very truly yours, John E. Maier

'," 8402070380 840isi PSR ADOCK 05000244,,/

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January 1984 ROCHESTER GAS 8 ELECTRIC USNRC REG.

GUIDE 1.97 REVISION 2 COMPARISON REPORT Variable Required Ran e

NRC Cate o

Present Ginna Status Neutron Flux Control Rod Position 10 to 100/ power Full in or not full in Existing NIS not qualified to Category 1

Existing RCS Soluble Boron Concent.

RCS Cold Ieg Temperature RCS Hot Leg Temperature RCS Pressure Core Exit Temperature 0-6000 ppm 50"750 F 50-750 F 0-3000 psig 200"16500F Available on PASS, System Range:

50-6000 ppm TW-450 and 451 aze not quali-fied to Category 1; indication on Main Control Board is by recorder TR-410 (range 0-700 F)

No,direct control room readout existing.

Have cold leg temperature and delta T and qualified hot leg temperature to subcooling meter.

PT-420A feeds PR-429 (0-3000 psig) and is Category 1;

PT-420 feeds PR-420 (0-.3000 psig) but is not powered from Category I source.

Existing 39-chromel-alumel thermocouples positioned over outlet nozzles at selected core locations.

Range:

40-700 F on control board indicator, up to 1200 F on computer for all TCs and up to 2200 F on computer for 5 TCs.

Future, system upgrade will provide indication through entire required range.

Current system not qualified to Category l.

Coolant Level in Reactor Degrees of Sub-cooling Core bottom to 1

top 200~F sub-cooling to 35 F superheat Not currently existing; system being designed

Existing, (range:

0-100~F subcooling)

jI I

rt P'

January 1984 Variable Required Ran e

NRC Cate o

Present Ginna Status Containment Sump Narrow Range Containment Sump Bottom of con-1 Wide Range tainment to 600,000 gallon level

Existing, Sump A:

LT-2039 and LT-2044 (range:

0-30 ft.)

Existing, Sump B:

LC-942(A-E) and LC-943(A-E) indication of 8, 78,113,

180, 214 inches (214 inches

= approx.

500,000 gal.

which was previously justified and accepted by NRC).

Containment Pressure 10 psia to 3 times design pressure Existing, PT-946 6 948 (10-200 psia)

Containment Isolation Valve Position Closed/not closed Existing, white status lights on HCB and backlighted push-bottons on CI matrix panels Radioactivity Concentration or Radiation Ievel in Circulating Primary Coolant 1/2 to 100 times Tech.

Spec. limit R/}lr

,Available with PASS system.

Analysis of Primary Coolant Containment Area Radiation 10 to 10 Ci/gm or TID-14844 source term in coolant volume 1 to 10 R/hr 1

7 Existing capability Existing Radiation 10 to 10 R/hr 2

-1 4

Exposure Rate (areas where access required to service equipment)

Radiation meters provided (or will be provided) where

,post-accident operator access required.

Ranges meet dose rate calculated using TID 14844 source term.

Based on single failure considerations no access required to service equipment.

Effluent Radio-activity-Noble Gas:

-Condenser Air Ejector Exhaust

-Containment Purge Vent Exhaust 10 to 10

-6 uCi/cc 10 to 10 uCi/cc Existing Existing

" 2-

,J C,

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January 1984 Variable Required Ran e

NRC Cate or Present Ginna Status

-Plant Bldg.

Exhaust Vent

-Vent from S/G Safety Relief 8 Atmospheric Dump Valves Effluent Radio-activity-Particulates and Halogens.

Sampling with Onsite Analysis Capability:

-Containment Purge Vent Exhaust 10 to 10 uCi/cc 10 to 10 uCi/cc 10 to 10 uCi/cc Existing Existing Existing

-Aux. Bldg.

Vent Exhaust Containment Hydrogen Concentration 10 to 10 uCi/cc 0-10'j, Existing Existing Radiation Exposure Rate in Areas Adjacent to Containment 10 to 10 R/hr Area monitors existing in Aux. Bldg. agd Int.1Bldg.

(range:

10 to 10 R/hr)

RHR System Flow 0-110/ design 2

Existing, FT-626 (0-4000 gpm)

RHR Heat Exchanger Out-let Temperature Accumulator Tank Level and Pressure Accumulator Isol. Valve Position Charging Flow 32-350~F 10-90/ volume 2

0-750 psig Closed or open 2

0-110$ design 2

Existing, TE-627 to computer (range:

0-310~F)

Narrow range instrument indicates

+7 inches from normal filllevel for accurate Tech.

Spec.

compliance; 0-800 psig pressure

Existing, MOV 841 Sr 865 position indicated on MCB Existing,FT-128 (0-75 gpm, the maximum flow anticipated in normal operations)

g Ih II

January 1984 Variable Required Ran e

NRC Cate or Present Ginna Status SI Flow RWST Level

, Reactor Coolant Pump Status Primary System Safety Relief Valve Positions (PORV's 6 Code Safeties)

Pressurizer Level 0-110$ design 2

,Top to bottom 2

Electric current Closed/not closed Bottom to top Existing FT-924 6 925 (0-1000 gpm)

Existing, LT-920 8 921 (0-100/)

Ammeter existing at 4KV Bus (0"1200A)

Existing Existing Pressurizer Heater Status Quench Tank Level Electric current Top to bottom 3

For control group of heaters, ammeter existing in Aux. Bldg.

No ammeter for backup group, but-have breaker position for both'ontrol and backup groups in Control Room.

Existing, LT"442 (0"100$)

Quench, Tank Temp.

Quench Tank Pressure S/G Level S/G Pressure Safety/Relief Valve Positions or Main Steam Flow 50-750oF 0 to design pressure Tubesheet to separators From atmos-2 pheric press.

to 20/ above lowest safety valve setting (1300 psig)

Closed/not closed Existing, TE-439 (0-300~F)

Existing, PT-440 (0-150 psig)

Exist'ing, LT-'460 8 470'nput to LR-460 on MCB (0-518" H 0) 2 Existing, PT-468,

469, 478, 479 (range:

0-1400 'psig)

Existing, main steam flow FT-464, 46$, 474, 475 (range:

0-3.8 x 10 pph).

Safety/

relief. valve positions only during high ra'diation in s'econdary sys.

h

January 1984 Variable Required Ran e

NRC Cate o

Present Ginna Status Main Feedwater Flow Aux. Feedwater Flow 0-110'/ design 3

0-110% design 2

flow Existing, FT-466, 4]7, 476, 477 (range:

0-3.8 x 10 pph)

Existing Condensate Storage Tank Plant Specific 1

CST Transmitters LT-2022A and LT-2022B are qualified; read 0-24 ft.

Containment Spray 0-110'/ design 2

Flow flow Existing NaOH flow, FT 930 and tank level, LT 931.

No total spray flow.

CV Fan Heat Removal CV Atmosphere Temp.

Plant Specific 2

40-400 F CV fan 1A, 1B, 1C, 1D on/off status 'at MCB, plenum exhaust temp.

24 CV RTD's go to Leak Rate Test Panel; range 130oF Also, RTD's in plenum exhaust read 0-600oF CV Sump Water Temp Makeup Plow (Charging) 50-250 F 0-110$ design 2

Not existing PT-128 (0-75 gpm, the maximum flow anticipated during normal

operation)

Letdown Flow 0-110/ design 2

Volume Control top to bottom 2

Tank Level FT-134 (0-100 gpm)

LT"112 (0-100$ )

Component Cooling 32-200~F Water Temp. to ESF TE-621 from CCW Hx goes,to

'computer (50"200~F)

High Level Radioactive Tank Level top to bottom 3

L1001 (0-.100/)

Radioactive Gas 0 to 150/ design 3

Holdup Tank Pressure

. Emergency Vent Open/close Damper Position status

P1036, 1037)

1038, 1039 (0-150 psig) design pressure 150 psig, normal operation 100-110 psig.

Existing for containment vent on MCB

N4',

III

January 1984 Variable Required Ran e

NRC Cate or Present Ginna Status Status of Standby Power and Other Energy Sources Impor'tant to Safety (hydraulic,

'pneumatic):

-480 V Bus Voltage, current 2

pressure Existing diesel voltmeters 8

ammeters on MCB

-Instrument Bus Existing voltmeters on panels in control room; ammeters on inverters in battery rooms for bus lA 8 1C

-125 VDC Bus Existing voltmeters and ammeters in Control Room Radiation Expo-sure Meters (continuous

,indication at fixed locations)

Range, location, 2

and qualifi-cation criteria to be developed to satisfy NUREG-0654)

'Section II.H.5b and 6b requirements for emergency radiological monitors Existing procedures and equipment are used

.to initiate emergency

.measures in accordance with Appendix I and II.H.5b and 6b of NUREG 0654 and NRC approved plant Technical Specifications for compliance with 10 CFR 50 Appendix I.

Airborne Radio-halogens and Particulates (portable sampling with onsite analysis capability) 10 to 10 uCi/cc Existing Plant and Environs Radi-ation (portable instrumentation) 10 to 10 R/hg) photgn 10 to 10 rads/hr, beta radiations and low energy photons Existing January 1984 Variable Required Ran e

NRC Cate o

Present Ginna Status Plant and Environs Radioactivity (portable instrumentation)

Wind Direction Wind Speed Estimation of Atmospheric Stability Multichannel gamma ray spectrometer 0-360 0-67 mph Based on vertical temperatures differences Existing Existing Existing at 33,

150, 250 ft.

elevations (range:

0-100 mph)

Existing, 2 RTD's at 33,

150, 250 ft. elevations; delta T

between each elevation Primary Coolant and Sump:

-Gross Activity

-Gamma Spectrum

-Boron Content

-Chloride Content Grab Sample 10 to 10 Ci/cc Isotopic Analysis 0-6000 ppm 0-20 ppm Available with PASS system Existing (50-6000 ppm) with PASS 5 ppb - 100 ppm lab analysis

-Dissolved Hydrogen

-Dissolved Oxygen

-pH Containment Air:

-Hydrogen Content 0-2000 cc(STP)/Kg 0-20 ppm 1-13 Grab Sample 0-10%

(10-2000 cc/Kg) with PASS (0.1 - 20 ppm) with PASS 1-13 with PASS Available with PASS Available with H2 monitors and PASS

-Oxygen Content 0-30%

-Gamma Spectrum Isotopic Analysis 0-30% with PASS Existing

I