ML17262A881
| ML17262A881 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 03/13/1992 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Hodges M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 9206150043 | |
| Download: ML17262A881 (34) | |
Text
N TRATION SYSTEM REGULATE'NFORMATION DISTRZBUTIOlYSTEM (RIDE)
ACCESSION NBR:9206150043 DOC.DATE: 92/03/13 NOTARIZED: NO DOCKET FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.
RECIP.NAME RECIPIENT AFFILIATION HODGES,M.W.
Region 1 (Post 820201)
SUBJECT:
Forwards response to NRC 910322 request for clarification of util position on implementation of Reg Guide 1.97,Rev 3
Suppl 1 to NUREG-0737, "Comparison of Post-Accident Instrumentation."
DISTRIBUTION CODE:
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- >> 4 VA>>>>ll'J u ROCHESTER GAS AND ELGCTRIC CORPORATION
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89 EAST AVENUE, ROCHESTER N. Y. 14649-0001 ROBERT C.!>sECREDY
'>ice Presnsenr
>;:nne >ruereer Pros>ver>rsn March 13, 1992 KtEPHOsrE GAEAcooE 716 54r27OQ U.S. Nuclear Regulatory Commission Attn:
Marvin W. Hodges Director, Division or Reactor Safety 475 Allendale Road King of Prussia, PA 19406 0
Subject:
NUREG-0737 Supplement 1/Regulatory Guide 1.97:
Comparison of Ginna Pos" Accident Instrumentation R.E.
Ginna Nuclear Power Plant Docket No.
0-244 Ref.
Letter from M. Hodges (NRC) to R. Mecredy (RG&E),
i a Stati ns n >c
~
e to Regulat'r~ Guide 1.97, revision 3," dated March 22, 1991.
Ref.
2.
Letter from R. Mecredy (RG&E) to M. Hodges (NRC),
same subjec~,
dated May 16, 1991
Dear Mr. Hodges:
By letter dated Marcn 22, 1991 (Reference 1), your office requested information clarifying RG&E's position regarding implementation of Regulatory Guide 1.97, revision 3 at Ginna-Stacion.
Reference 2 provided a detailed response to this request.
As part of this response RG&E offered to provide a
comparison of existing Ginna Station instrumentation attributes with the criteria provided in Regulatory Guide 1.97, revision 3.
Attachments 1,
2, and 3 of this letter provide this comparison.
Attachment 1 details how RG&E categorizes post accident instruments and what qualification is applied to these categories.
Attachments 2 and 3 provide a comparison of the variables and criteria provided in Regulatory Guide 1.97, revision 3 Table 3 to post accident instrumentation at Ginna Station. It should be noted that this effort has resulted, in eclassifying Pressurizer Safety Valve Position indication as a
Type D variable (previously Type A).
This new classification is consistent with Regulatory Guide
~.97 revision 3.
r.~i>
>~v v i)'J F DR
+3 92p3g 3 92pgg g p
4DOCg pgpp PDR rgv/
As previously stated, RG&E wishes to emphasize that this comparison does not imply a commitment to Regulatory Guide 1.97.
we feel that NUREG 0737 supplement 1 is the appropriate basis for post accident instrumentation criteria at Ginna Station.
Very truly yours,
~n Robert C. Mecredy BJF/215'ttachments xc:
'J.S.
Nuclear Regulatory Commission Document Control Desk Attn:
Mr. Allen R. Johnson (Mail Stop 14D1)
PWR Project Directorate i-3 Washington, D.C.
20555 Ginna Senior Resident Inspector
Attachment 1
RGErE Post Accident Instrumentation/Regulatory Guide 1.97, Rev.
3 Comparison of Classification, Categorization and Qualification Criteria I.
Classification Post accident instrumentation at Ginna is classified according to the following criteria:
Type A:
indication required by the operator during performance of an Emergency Operatin~ Procedure (EOP), in response to a desi basis accident, to determine ifmanual actions are required in order to accomplish required safety functions forwhich no automatic action is provided.
Type B:
Indication used by the operator during performance ofan Emergency Operating Procedure (EOP), in response to a design basis accident, to verify that required automatic or manual safety functions have been accomplished.
Type C:
Indication used by the operator during performance of an Emergency Operating Procedure (EOP), in response to a design basis accident, to determine ifany of the barriers to fission product release have been, or may be breached.
Type D:
Indication used by the operator during performance of an Emergency Operating Procedure (EOP), in response to a design basis accident, to determine that a safety system or system important to safety has actuated.
Type E:
Indication used by the operator to determine the magnitude of a radioactive release, and to continually assess the release.
RG&E believes this to be consistent with Regulatory Guide 1.97, revision 3.
, continued Categorization Category 1:
Category 2:
Category 3:
Type A variables and key (primary) Types B and C variables make up Category 1.
Key (primary) Types D and E variables make up Category "
Backup Types B. C, D and E variables make up Category 3.
RGRE believes this to be consistent with Regulatory Guide 1.97, revision 3.
3.
Equipment Qualification Environment:
Those portions of Category 1 or 2 post accident instrumenta-tion channels located in harsh enviro. ments are qualified f~",
their design basis accident environments in accordance with the Ginna 10CFRS0.49 Environmental Qualification Program.
Design Basis Accident Environments are specified in the Ginna UFSAR Table 3.11-1.
Those portions of post accident instru-mentation channels located in mild environments do not require environmental qualification.
Seismic:
Category 1
post accident instrumentation is seismically qualified in accordance with the Ginna Seismic Qualification Program (UFSAR Chapter 3.10) with the following clarifica-tions:
Seismic qualification foranalog indicators was generally not provided for those indicators in place before 1983 regardless of category.
Only those portions of the channel that performed a safety function (i.e. RPS or ESF actuation) were qualified.
2.
3.
Seismic qualification is not considered necessary for recorders unless they provide the sole indication for a Category 1 variable.
1 Seismic qualification for inputs to the plant process computer is provided only up to the isolating device feeding the computer input. The SAS/PPCS is not seis-micaiiy qualified.
Only the mounting of status light housings is consid-ered seismically qualified. Light bulbs are considered "commercially rugged" and can be reasonably expected to survive an earthquake.
, continued 4.
Redundancy Redundant channels are provided for Category 1 post accident instrumentation channels.
Each redundant channel is electrically independent.
Physical separa-tion between redundant channels in the field is maintained in accordance with the Ginna design criteria in effect at the time of the equipment's installation, for the classification of the equipment at that time. If the classification of installed equipment changes, the need to provide separation is analyzed on a safety impact basis.
Therefore, field separation may not be provided for all category 1
redundant channels.
Physical separation is not maintained in the control room.
Withineach redundant division of a safety system, redundant monitoring channels are not required except for steam generator wide range level.
5.
Power Source Instrumentation at Ginna generally receives power from ""e of eight sources.
1.
2.
3.
4.
5.
Go 7.
8.
Instrument Bus 1A (safety related battery backup)
Instrument Bus 1B (safety related emergency AC backup)
Instrument Bus 1C (safety related battery backup)
Instrument Bus 1D (non safety related)
Inverter MQ-483 (safety related battery backup)
Technical Support Center (T.S.C.) battery bus
'A'25 V dc safety related battery bus
'B'25 V dc safety related battery bus Instrument Buses 1A, 1B, 1C, Inverter MQ-483, 'A'25 V dc bus, and 'B'25 V dc bus are considered safety related power sources suitable for all post accident instrumentation categories.
The TSC batter y bus is considered a highly reliable power source suitable for Categories 2 and 3 variables.
Instrument bus 1D is considered a
reliable power source suitable for Category 3 variables.
The Safety Assessment System/Plant Process Computer System (SAS/PPCS) receives power from the TSC battery.
RGRE believes this to be consistent with Regulatory Guide 1.97, revision 3.
, continued 6.
Channel Availability Instrument channel availability and allowable out of service times are in accor-dance with Ginna technical specification requirements for the associated system when the instrument channel operability is necessary for the functionality of the system. Specific Technical Specifications are provided in table 3.5-3 for severa.
post accident instrument channels.
RG&E believes this to be consistent with Regulatory Guide 1.97, revision 3.
7.
Quality Assurance RG&E maintains an approved 10CFR50 Appendix B Quality Assurance Program which is based on the ANSI/ANS 51.1 Standard.
Three quality categories exist:
1.
Safety. Related Class (SR) 2.
Safety Significant Class (SS) 3.
Non-Safety Class (NS)
Criteria for safety classification is contained in the Ginna. Station Quality Assurance Manual Appendix A. The Safety Related C!ass (SR) provides for ful~}
program control and is considered suitable for any category of post accident instrumentation.
The Safety Significant Class (SS) provides augmented quality control based on the importance to safety of the device or activity and is considered suitable for categories 2 or 3 variables, and certain portions of category 1 channels (recorders, secondary'ndicators)
The Non-Safety Class (NS) provides normal commercial grade quality control which may be suitable for some category 3 variables.
Procurement of post accident instrumentation equipment currently installed was in accordance with the Quality Assurance Program in effect at the time of the pro-curement for the classification of the equipment at that time.
Future procure-ment, maintenance, calibration, and design controls willbe in accordance withthe program as described above.
8.
Display/Recording Several types of display instrumentation are available:
5.
6.
Analog Indicators Digital Indicators Strip Chart Recorders Safety Assessment System/Plant Process Computer System (SAS/PPCS)
Multipoint Recorders Status Lights
, continued All types of instrumentation may be suitable for any category of post accident instrumentation.
The SAS/PPCS has the capability ofproviding historical trends of any available channel and is considered a suitable recording device for any category of post accident instrumentation. Variables recorded at Ginna, and the capabilities of the recording devices were provided to the NRC in response io Generic Letter 83-28 Item
- 1. 2, "Post-Trip Review:
Data and Information Capability". The acceptability of this configuration is documented by NRC SER dated November 5, 1990.
Recording of digital inputs (e.g., breaker lights, valve position) regardless o,
category is generally not provided.
Decisions regarding whether or not recording is provided, and what type of recording is provided is based on the Ginna Emergency Operations Procedures and the abilityof the device to capture all significant transient response informa-tion associated with the specific variable.
RGErE believes this to be consistent with Regulatory Guide 1.97, Revision 3.
9.
Range Post accident instrument ranges are selected based on both normal operational requirements foraccuracy and readability, and also so that the indication remains on scale for design basis accident conditions ifpracticable.
In some situations multiple instruments with overlapping spans are provided to accomplish this.
Range requirements for "beyond design basis accidents" are evaluated and are provided for on a safety benefit basis.
10.
Equipment Identification Labelling of instrumentation at Ginna is in accordance with the Ginna Human Factor's Program.
Common designation of post accident instrumentation is not provided.
Common designation would only be appropriate where several redundant instrument channels are provided ofwhich only a few are post accident qualified. This is generally not the case at Ginna.
Interfaces For post accident instrumentation that is part of a safety related system, isolation is provided between those safety related portions of the channel and the in-dication.
Isolation between post accident indication and other uses (controllers, alarms) is not nece'ssarily provided.
, continued 12.
Servicing, Testing, and Calibration:
Periodic
- checking, testing, calibration, and calibration verification are in accordance with Ginna Technical Specifications tables 4.1-1, 4.1-2, and 4.1-3 vhere applicable.
Calibration frequencies are specified in order to maintain the functionality of the monitoring instrument, and are adjusted as dictated b-historical data.
RGB,E believes this to be consistent with Regulatory Guide 1.97, Revision 3.
13.
Human Factors Post accident instrumentation types and locations are in accordance withthe RGRE Human Factors Program and Detailed Control Room Design Review, which has been approved by the NRC.
RG8rE believes this to oe consistent with Regulatory Guide 1.97, Revision 3.
14.
Direct Measurement To the extent practicable direct measurement of monitored variables is provided.
When indirect measurement is used it is evaluated to ensure that unambiguous information is provided, such that resulting operator action is consistent with the action that would result if direct measurement of the variable were provided.
RG8rE believes this to be consistent with Regulatory Guide 1.97, Revision 3.
BJFK012 Explanation of Table 1 Entries Table 1 consists of thirteen entries for each variable: a sequential number (g), the variable type (TYPE), the variable description (VARIABLE), category (CAT),
range (RANGE), the equipment environmental qualification status (EEQ), seismic qualification status (SEISMIC), the quality assurance-program classification of the equipment (QA), the power source for the channel (P.S.), whether or not there is control room indication of the variable (CR IND), whether or not recording is provided via discrete recorders
{CHART), or the plant process computer {COMP) and any comments on the variable (COMMENTS).
Entries in bold are from Regulatory Guide 1.97, revision 3.
Entries below each bold entry depict Ginna Station configurations.
Any entries in parenthesis represent proposed configura-tions not currently installed.
Specific entries are explained below:
TYPE RG 1.97:
B,C,D,E as in Regulatory Guide 1.97, revision 3.
(n.a.
is entered for Type A. variables since they are not provided in the guide)
Ginna:
A,B,C,D,E as described in the classification section of Attach-ment 1. (n.a. is entered for variables that although listed in Regulatory Guide 1. 97, revision 3, are not considered post acci-dent variables at Ginna Station).
VARIABLE RG 1.97:
Ginna:
description as in Regulatory Guide 1.97, rev.
3 C
equipment identification numbers of the primary instruments which monitor the variable.
CATEGORY RG 1.97:
1,2,3 as per RG 1.97, rev.
3 Ginna:
1,2,3 as per Ginna Station post accident instrumentation categorization (see attachment
- 1). Ifthe channel is not consid-ered post accident instrumentation at Ginna (n.a. under TYPE) then this entry represents the current level of qualification of the channel.
, continued RANGE RG 1.97:
'plant specific'range'ange not specified in Rg 1.97 rev.
3 range as specified in Rg 1.97, rev.
3 Ginna:'range'ange of primary indicator used to monitor the variable at Ginna Station RG 1.97:
yes no 1
signifies environmental qualification inaccordance with RG 1.89 is recommended signifies environmental qualification is not required Ginna:
yes no mild (yes) signifies environmental qualification inaccordance withthe Ginna Station 10CFR50.49 compliance program (UFSAR Section 3.11) is provided signifies environmental qualification is not provided signifies the primary device is located in a mild environ-ment during its post accident function and therefore environmental qualification is not provided signifies environmental qualification in accordance withthe Ginna Station 10CFR50.49 compliance program is planned but not yet complete.
SEISiblIC
-RG 1.97:
yes no signifies seismic qualification in accordance with Rg 1.100 is recommended signifies seismic qualification is not required Ginna:
yes
, 'no (yes) signifies seismic qualification in accordance with the Ginna Seismic qualification program is provided.
Seismic qualifi-cation at Ginna is currently being resolved under USI-46.
signifies seismic qualification is not provided'ignifies seismic qualification is proposed but not yet provided Seismic qualification only applies to the primary variable indication and those portions of the instrument loop necessary for this indication to function.
Recorders are not seismically qualified unless they are the primary indicator.
The plant process computer is not seismically qualified.
, continued QA Category RG 1.97:
full partial comm Quality Assurance in accordance with RGs 1.28, 1.30, 1.38, 1.58, 1.64, 1.74, 1.88, 1.123, 1.144, and 1.146 is recommended.
Quality Assurance commensurate with the importance to safety of the instrument should be provided.
Quality Assurance through high quality commercial practices should be provided.
Ginna:
POEIjER SUPPLY RG 1.97:
SR NS 1E
( SAFETY RELATED)Quality Assurance inaccordance with the Ginna Station 10CFR50 Appendix B QA program for safety related devices.
(see attachment 1)
(SAFETY SIGNIFICANT)QualityAssurance in accordance with the Ginna Station 10 CFR50 Appendix B QA program for devices important to plant safet'r.
'~ee attachment V (NON-SAFETY) Quality Assurance provided through commercial control practices and not covered under the Ginna Station 10CFR50 Appendix B QA program.
power provided in accordance with RG 1.32 with battery backup if momentary loss cannot be tolerated should be provided Ginna:
rel nepo 1B a high reliability power source with battery backup if momentary loss cannot be tolerated should be provided.
no provision made in RG 1.97 rev.
3 A safety related power supply (1E) provided from instru-ment bus lA. Safety related battery A supply precludes momentary loss of power.
A safety related power supply (1E) provided from instru-ment bus 1B.
Ão battery backup is provided.
Emergency onsite power is provided by Emergency Diesel Generator A.
1C MQ-483 A safety related power supply (1E) provided from instru-ment bus 1C.
Safety related battery B supply precludes momentary loss of power.
A safety related power supply from inverter MQ-483.
Safety related battery A supply precludes momentary loss of power.
, continued 1D A non safety related power supply from instrument bus 1D. No battery backup is provided, nor emergency onsite source.
TSC Ahighly reliable onsite power source withbattery backup to preclude momentary loss of power ADC BDC Safety Related battery bus A Safety Related battery bus B C.R. IND RG 1.97:
Ginna:
yes no Ilies no continuous realtime display should be provided continuous display in the control room is not necessary Contxol Room indication, separate
~"."m a recorder
's provided Control Room indicator (other'han plant process computer or recorder) is nox provided.
note: the equipmenz identification number is provided if appropriate.
RECORDER RG 1.97:.
'plant specific'ecorder shall be provided if trend information on the variable is used by operators duxing post accident recov-ery.
no recording is not required Entries for Ginna are subdivided between CHART and COMP:
CHART Ginna:
yes no a control room recorder is provided.
The equipment identification numbex is provided ifappxopriate no recorder is provided
, continued COMP Ginna:
yes the variable is available on the plant process computer.
(The point identification is given ifappropriate)-
no the instrument does not input to the computer.
8JF/021
/t TYPE VARIABI.E Attachment 3
Table l Comparison of Glnna Post Accident lnstrume>>tatlon to Regulatory Guide 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
" IND.
CllART COblP COhtMENTS Page I of 20 n.a.
Aux Feedwster Flow 1
Plant Specific y es yes full 1E, yes Plant Specific A
Ff-2001 (MDAFW/SGA)
I 0 - 275 gpm (0-138%)
FT-2013 (MDAFW/SGA)
I 0 - 275 gpm (0-138%)
Fi'-2002 (MDAFW/SGB)
I 0 - 275 gpm (0-138%)
FT-2014 'fMDAFW/SGB)
I 0 - 275 gpm (0-138%)
Fi'-2006 (fDAFW/SGA)
I 0 - 500 gpm (0-125%)
Fl'-2007 (TDAFW/SGB)
I 0- 500 gpm (0-125%)
mild ycs mild ycs mild ycs mild ycs mild ycs mild yes SR SR SR SR SR SR IA H-2021 A IC Fl-2029 IC 11-2022A IA 11-2030 IC I'1.2023A IA 11-2024 A no no no no no no F2021 two pcr redundant function provided F2029 F2022 F2030 F2023 F2024 also satisfies ff69 2
n.s.
Standby Aux. I:eed l
l'lant Specific yes yes full 1 E yes Plant Speclflc A
FT-4084 FT4 085 I
0-250 gpm (0-125%)
I 0-250 Ilpln (0-125%)
mild ycs SR IA 114084 no, F4084 one pcr redundant function provided mild ycs SR IC I'14085 no F4085 Core Exit 3
n.a.
Thermoci>upies A
Tl -T39 1
l'lant Specific I
0-2300 'F yes yes full I E yes Plant, Specific ycs ycs'R IA
(:1."I'A no ycs IC
(:I.lB 39 CET's are provided. Technical Spccil tcations require a minimum of lo>>r-operablc per qtmdrant. 19 CE1's are associated with thc A train and 20 with the B Train.
Containment
)Hgh 4
n.a.
Radiation Monitor A
R29 R30 I
Plant Specific I
I R/hr - IE7 R/hr I
I R/hr - IE7 R/hr yes yes full 1E
.yes Plant Specific ycs yes SR IA RM-29 yes R29 yes yes SR IC I:M-30 yes R30 also satisfies ff's 30,37 Containment 5
n.a.
Hydrogen Monitor 1
Plant Specific yes yes
. full lE yes Plant Specific
,also sausfies ttem N84 A
CONTH2MONT-IA
'ONG12MONT-IB I
0-10%
I 0-10 %
yes yes SR IA no yes'es yes SR IC no yes~
CVHA s although the recorders are t'ne only control CVHB coom indication of Containment H2 concemration, they are not considered th primary indicator. The H2 Monitorpanels in thc.:city room provide pricnary indication.
als i satisfies item N6
¹ TYPE VARIABLE Attachment 3
Table I Comparison of Glnna Post Accident Instrumentatlon to Regulatory
('ulde 1.97, Revision 3 Crlterla C.R.
RECORDER CAT."
RANGE EEQ SEISMIC QA P.S.
IND.
CIIART COMP COMMENTS Page 2 ol'20 6
n.a Containment Pressure I
Plant Speclflc yes yes full l E yes Plant Speclflc A
Fi'-945 Fr-946 FI'-947 Ff-948 Fr-949 FI'-950 I
0-60 psig I
10-200 psia I
0-60 psig I
I0-2($ psia I
0-60 psig I
10-2($ psia ycs ycs ycs ycs ycs ycs yes yes ycs ycs ycs ycs SR IA PI-945 SR 18 Pl-946 SR IC PI-947 SR IC PI-948 SR IB PI-949 SR MQ483PI-950 no
. P0945 ntcse recorders are proposal to be removed ycs'o with inputs to the SAS/PPCS provided no P0947 instead.
yes'o no I'0949
'o no also satisfies items ¹35,41 Condensate Storage 7
n.a.
Tank I.evet A
LT-2022A (tank A)
LT-20228 (tank 8)
I Plant Speclflc I
0-24 ft I
0-24 ft yes yes full lE yes Plant Speclflc mild ycs lull (l yCS SR IA LI-2022A no L2022A The transmitters are not located in a Seismic SR
- IC I.1-31228 no no Category I building. The tanks are conncctcd by a locked open 10" line.
8 n.a.
Pressutlzer I'ressure I
Plant Speclflc yes y<n>erll 3
Table I Comparison of Glnna Post Accident Instrumentatlou lo Regulator)>
Guide
).97>
Revision 3 Crlterla C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
C)IART COMP COMMENTS Page 3 of 20 RCS Cold Leg 1 I n.a Temperature 1
Plant Specific yes yes full 1 E y e s Plant Speclflc A
TE~B-I (Loop A)-
TEA108-1 (Loop 8)
I 0-700 oF I
0-700'F yes ycs yes yes SR IA TI4098-I no no SR IC TIP)08-I no no RCS Hot Leg 12 n.a.
Temperature I
Plant Specific yes yes full
)E yes I'lant Speclflc also satisfies item N28 A
TE409A-I (Loop A)
I 0-700 'F TEAIOA-I (Loop 8)
I 0-700 'F yes yes SR IA TI409A-I no T0409A ycs ycs SR IC TIPIOA-I no TMIOA also satisfies item N27 13 n.a.
RCS Pressure A
Fl'-420 Pf-420A I
Plant Speci l'lc I
0-3000 psig I
0-3NN) psig yes yes full
)E, yes Plant Specific ycs ycs SR 1A I'1420 PR420 P0420 ycs ycs SR IC I'1420A PR-420A I'0420A R)IR Flow (low 14 n.a.
pressure Injection)
I Plant Speclflc y es yes full I E yes Plant Speclflc also satisfies items N29,40 A
FI'-626 I
0- 4000 gpm g7-xxx)
(I)
(0 - 4000gpm)
Fl'-931A (Loop A)>>
I 0 - 2200 gpm FT-9318(LoopB)
I 0-22(Sgpm ycs yes SR IC FI426 (yes)
(ycs)
(SR)
(IA)
(ycs) ycs ycs SR IC 11-931A ycs ycs SR 18 I1-93)8 FR-626 F0626 'I'-931A and FI'-93IB are RHR suction (no)
(yes) flows from the Containment sump.
no no Aredundant flow transmitter to FT-626 no no utilizing the same primary element is proposed.
also satisfies items 049, 56 Reactor Vessel Level 15 n.a.
Indlcatlon System 1
Plant Speclflc yes yes full 1E yes Plant Speclflc A
LT490A LT4908 I
0-100%
I 0- 100%
yes 'es SR IA LI490A yes yes SR IC IW908'o no L0496A RVLIS receives 'correction'nputs fmm sensor LN968 line temperature, RCP status, and RHR flow.
Where both channels have common inprits thc input signals to each chanrel are isolaterl.
als
> s'<<rsflcs <<cm 031
TYPE VARIAIII.E EEQ SEISMlC Attachinent 3
Table I Comparison of Glnua Post Accident Instrum<<ntatlon to Regulatory Guide 1.97, R<<vision C.R.
RECORDER QA P ~ S.
IND~
CIIART COMP 3 Crlterla COMMENTS Pat,o 4 ol'20 16 n.a.
'Refueling Water Storage Tank LT-920 LT-921 I
Plant Speclftc I
0- 100%
I 0- 100%
yes yes mild yes mild ycs Iu II SR SR IE IC~
IA yes LI-920 1.1-921 Plant Specific no L0920 no L0921
~ Computer indication of this channel also requires power lrom IA.
17 n.a.
Safety Injection Flow
()II Press.
In)ection)
I Plant Specific yes yes yes Plant Speclflc also satisfies item ¹57 FT-924 (SIP 8)
Ff-925 (SIP A) l 0-1000 gpm I
0-1000 gpm yes ycs ycs ycs SR SR IA Fl-924 IB, 1C Fl-925 no F0924A no F0925A 18 n.a.
Steam Generator Range I.evel LT-501 (SG A)
I.T-505 (SG A)
LT-506 (SG 8)
LT-507 (SG 8)
Wide I
Plant Speclflc I
0-100%
I 0.100%
I 0-100%
I 0-100%
yes yes ycs
'jjcs yes ycs ycs yes yes yes Iu I I SR SR SR SR IE 1A IC IA 1C yes 1.1-504 1.1-505 l.1-506 1.1-507 I'lant Specific LR-504 LOSN I.R-505 L0505 LR-506 L0506 LR-507 L0507 also satisfies item ¹55 Two per Steam Generator required for two loop plants Two per Steam Generator provided.
19 n.a.
Steam Generator Narrow Range Level I
Plant Specific yes yes full IE yes Plant Speclflc also satisfies item ¹65 LT-461 (SG A)
LT462 (SG A)
LT-463 (SG A)
LT471 (SG 8)
'T472(SG 8)
LT473 (SG 8)
I 0-100%
I 0-100%
1 0-100%
I 0-100%
1 0-100%
I 0-100%
ycs jjes yes ycs ycs ycs yes yes yes yes yes ycs SR SR SR SR SR SR IA IC ID ID IA IB 1.1461 l.1462 l.l463 I.I471 LI472 LI473 yes~
yes~
yes+
yes~
yes~
yes~
L0461 L0462 L0463 LN7l L0472 L0473
'v Median of3 channels per generator is recorded.
Although channels LT-463 and LT471 are not powered from a safety related supply, they are maintained as catagory I variables in all other aspects.
also satisfies item ¹65 20 n.a.
Steam Generator Pressure I
Plant Speclftc yes yes fu II IE yes Plant Specific PI'468 (SG A)
PT469 (SG A)
PT478 (SG 8)
PT482 (SG A)
PT483 (SG 8) 0-1400 psig I
0-1400 psig I
0-1400 psig I
0-1400 psig I
0-1400 psig I
0-1400 psig yes
yes ycs yes ycs ycs yes ycs yes
- yes yes yes SR SR SR SR SR SR
- IA 18 F1468 PI469 IC I'1478 MQ4831'1479 IC I'1482A 18 I'1483A no P046S no P0469 no P0478 no P0479 no P0482 no
'P0483 also snusfies item ¹66
¹ TYPE VARIAftI.E Attachment 3
Table I Comparison of (itnna Post Accident Iustrumentatton lo Regulatory Gulrte 1.97, Revision 3 Criteria C.R.
RECORDER CAT.
"RANCiE EEQ SEISMIC (}A P.S.
IND.
CIIART COMP COMMENTS Page 5 of 20 21 u.a.
Steam Ftow I
Ptant S eclfic yes yes full lE yes Plant S ectfic A
FT-464 (SG A)
Fr465 (SG A)
Ff474 (SG B)
FI'-475 (SG B)
FI'-498 (SG A)
Ff499 (SG B)
I 0 - 3.8E6 pph I
0- 3.8E6 pph I
0- 3.8E6 pph I
0- 3.8E6 pph I
0 - 3.8E6 pph I
0 - 3.8E6 pph IA FI464 IB F1465 IC F1474 ID F1475 IA/IC 11498 IA/IC 11499 yes yes SR ycs>>
yes ycs SR yes'es ycs SR yes>>
ycs ycs SR yes>>
'o ycs SS yes*
no ycs SS yes'0464
<<Median of3 channels per SG is recorded.
F0465 FT475 power source is non-I Fhowever it F0474 satisfies all other Catagory I criteria. RGB E F0475 considers this acceptable because its protective I'0498 function is failsafe.
I:0499 also satisfies item ¹67 RCS Subcoottng 22 n.a.
Mon Itor I
Plant S ectfle yes yes foll I E yes I'tant S eclfle A
TI409A T1410A I
0- 100'F subccolcd ycs I
0-100'Fsubcoolcd ycs ycs S R IA f1409A ycs -
S R IC 1 1410A no TSUBA 'Ginna EOP's provide the means for no
'TSUBB determining subcooling based on Cps and RCS pressure. The SAS/PPCS also calculates subcooling using these variables. Both capabilities exceed the range recommendctl in RG 1.97, rcv 3. Also satisfies item ¹32 Containment Sump 23 n.a.
olde Range I.evel I 'lant Specific yes yec full 1E yes I'lant Specific A
LC-942 (A-E)
I.C-943 (A-E)
I 8, 78, 113, 180,214 in yes yes SR I
8, 78, 113, 180,214 in ycs.
yes Slk IA yes no yes Five discrete level switches per channel, 214 IC ycs no ycs inch indication corresponds to approximately 500,000 gallons.
also satisfies items ¹34, 43 24 It Neutron Flux I
IE-6 % -100 %power yes yes full IE yes Plant Specific B
N-31, N-32 (SR)
N-35, N-36 (IR)
N4IA,B; N-42A,B; N43A,B; N44A,B (PR) 3 IE-I to IE6cps (SR) 3 IE-11 tolE-3Amps (IR) 3 0 to lt6%power (PR) 3 no yes no ycs no ycs no yes SR>>>>
SR>>>>
SR>>>>
SR>>>>
IA/IB NI-31, 32 yes>>
IA/IB NI-35, 36 yes>>
IA/IB h;1-41,42 yes>>
IC/ID NI43,44 ycs'B rutfixfor MCB ind.)
yes Neutron flux indication is coitsidered a backup yes type B indication at Ginna and is therefore yes considcrel catagory 3.
yes>> Atwo pen recorder is provided with switchable inputs from all channels.
>>>> Protection portions of channels only.
25 8
Control Rod Position 3
full in or not full in no no comm. u..
uo no B
Microprocessor Rod Position Indication System (MRPI) 3 rod position indicated in twelve step increments, as well as indication of mds full in or not full in no no SS ycs no yes>> The MRPI system is powered from a dedicated transformer fjtom a satety relater I 480V MCC.
¹ TYPE VARIABLE Attachment 3
Table I Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revlslon 3 Crltcrla C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IN D.
CIIART COMP COMMENTS Page 6 ol 2U RCS Boron 26 B
Concentration 3
0 to 6000 ppm no no comm.
n.p.
no B
A14053 (Post Accident 3
50+50 - 60NB300 ppm no no S S
~
no Sampling System (PASS) Boron Analyzer) no no no
~ The PASS instrument panel is powered Rom 480 V bus 13 (non SR) via panel SB14.
NRC SER dated April 14, 1986 deferred the range and accuracy capabilities ofpost accident sampling systems to NUREG-0737, Item II.B.3. The Ginna PASS meet'hese criteria.
RCS Hot Leg 1Vater 27 B
Temperature I
50 'F - 700'I'es yes full I E y es Plant Specific
~ scc item ¹12, RG&EType A variable.
RCS Cold Leg IVater 28 B
Temperature 1
50 'F - 700'l'es yes full 1 E y e s I'lant Speclflc sce item ¹11, RG&E Type A variable.
29 B
RCS Pressure I
0 - 3000 pslg yes yes full,I E yes Plant Specific
~ see item ¹13, RG&E Type A variable.
30 Core Extt Temperature 3
200 'F - 2300 4F no no comm.
n.p.
no no
~ see item ¹3, RG&E Type A variable.
TYPE VARIABLE Attachment 3
Table 1
Comparison of Cstnna Post Accident Instrumentatton to Rcgulatury (lulde
- L97, Revlslon 3 Crlterla C.R.
RECORDER CAT.
RAN(lE EEQ SElSMlC QA P-S.
IND.
CllART COMP COMMENTS Page 7 of20 B
Coolant Inventory 1
liat l.eg bot.-
flange y e s y e s fu Il 1 E y es plant speclflc t
~ sce item ¹15, RG&E Type A variable.
RCS Degrees of 32 B
Subcoollng A
2 200'Fsub-35'Fsuper yes n o partial rel.
no no
~ sce item ¹22, RG&E %ape A variable.
Containment Sump 33 B
Level Narrow Range 2
Plant Specific yes n o partial rel.
n o no C
LT-2039 (Sump A)
LT-2044 (Sump A) 3 0-30 ft 3
0-30ft no no SS lA 1.1-2039 no L2039 NRC SER dated December 4, 1990 found the no no S S IA Ll-2N4 no L2044 instrumentation provided to b. acceptable.
Containment Sump 34 B
Level Wtde Range 1
Plant Speclflc A
yes, yes full 1E yes Plant Speclflc also satisfies item ¹42 a see item ¹23, RG&EType Avariable.
35 B
Containment Pressure 1
-5 pslg to design yes yes full 18 yes Plant Speclflc v'ee item ¹6, RG&E Type A variable.
note: The Ginna containmcnt prcssure indication covers a range of 10 psia to 3(O %
deign pressure.
Attachment 3
Table 1
Comparison of Glnna Post Ace!dent Instrumentation to Regulatory Guide 1.97, Revlslon 3 Crlterla C.R.
RECORDER tt TYPE VARIAttt.E CAT.
RANGE EEQ SFISMIC QA P.S.
IND.
ClIART COMP COMMENTS Page tt op20 Contain.
Isolation one per redundant function reqd. Check 36 tt
=
Valve Posltlon 1
closed I not closed yes yes full lE yes Plant Speelfle valve posltlon lnd.
ls not reqd.
B see UFSAR Table 6.2.13 3
open /closed for list ofcontainmcnt isolation valves.
Core Exit Temperature no yes SS
- ADC, ycs no yes BDC Isolation valves outside containmcnt go closed prior to being exposed to a harsh environment and therefore environmental qualification is not mqd.. RG&E has taken e>ception to the need to qualify indication for valves inside containment. Ref. letter RG&E-NRC 5/6/91.
37 C
200'F to 2300'F y e s y e s futl 1 E y e s Plant Speclflc
~ see item /f3, RG&E Type A variable.
38 C
RCS Radlatlon I.evel I
.5 IOOX Tech Spec yes yes full I E yes Plant Speclflc n.a..
Post Accident Sampling System (PASS), Manual Radiation Isotopic Spectroscopy after sample taken 3
0.01 mR - 1.0E04 R/hr n.a.
n.a.
SS n.a.
no no no NRC SER dated April 14, 1986 found thc instrumentation provided to be acceptable.
sce note 1.
Gamma Analysis of 39 C
Primary Coolant 3
1.0E-S 10 Ct/mt no no comm.
n.p.
no no C
Post Accident Sampling 1.0E 10 Ci/ml.
System g ASS), Manual Range can be extended Radiation Isotopic by dilution techniques.
Spectroscopy after sample taken n.a.
n.a.
SS n.a.
no no no NRC SER dated April 14, 1986 found the instrumentation provided to be acceptable.
40 C
RCS Pressure A
1 0 - 3000 pslg yes yes full 1E yes Plant Speclfle a see item ffI3,RG&E Type A variable.
¹ TYPE VARIABLE Attachment 3
Table I Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guble I.97, Revlslon 3 Criteria C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA I'.S.
IND.
CIIART COMP COMMENTS Page 9of 20 41 C
Containment Pressure I
-S pslg to design yes yes full I E yes I'lant Speclflc
~ sce item ¹6, RGkE Type A variable.
note: The Ginna containment Iiressure indication covers a range ofOpsig to 333%
design pressure.
Containment Sump 42 C
I.evel Narrow Range 2
top to bottom yes n o partial rel.
n o no
~ sec item ¹33, RGAE Type C variable.
NRC SER dated December 4, 1990 found thc insuurnentation provided to bc acceptable.
Containment Sump 43 C
Level 1VIde Range I
Plant Speclflc yes yes full I E yes Plant Speclflc
~ scc item ¹23, RG&E Type A variable.
Containment Area 44 C
Radiation E
R-2 3
I to 1.0E4 Rlhr 3
0.01 - 1.0ES R/hr no no comm.
n p.
no no yes SS 18 yes no yes R02 NRC SER dated April 14, 1986 found the instrumentation provided to be acccptablc.
Condenser Alr Exb.
45 C
Noble Gas Radloact.
2 IE-6 to IES pCllcc yes n o part.
rel.
no no E
R-15 R-15A (SPING) 2 1E-6 to 1E-3 ltCi/cc 2
lE-6 to 1 ES pCi/cc mild no SS 1D ycs yes R15 mild no SS R15A
TYPE VARIABLE Attachment 3
.,Table 1, Compartson of Glnna Post Accident Instrutnentattou to Regulatory Guide 1,97I Revtslou 3 Criteria C.R.
RECORDER CAT.
RANGE EFQ SEISMIC QA P.S.
IND.
CIIART COMP COMMENTS Page ]D of 20 Containment B2 46 C
Concentration OIO %
ycs yes full lE yes Plant Spcclfle
'cc item 85, RGB:E Type A variable.
Coutalnmeut Eff)uent 47 C
Noble Gas at Release 2
1EA to lE-2 pC)lcc pcs no psrtls) rel.
no no C
R-12 (Cont. Purge Vent) 2 IE4 to 1E-2 ltCitcc R-14 (Phnt Exh. Vent) 2 IE4 to IE-1 pCi/cc R-31 (SG Steam LincA) 2 lE-1 to lE3 pCike R-32 (SG Steam Line B) 2 lE-l to lE3 pCi/cc mild no S R IA yes mild no SS 1A ycs mild no SS
'ycs) mUd no SS
')m) ycs ycs 40 4o yes
'PING Monitors ar powered via a dedicat ycs tranformcr from MCC D (Safety Rclatcd).
ycs SPlNG monitors R-12A (Cont. Purge Vent) ycs and R-14A (Plant Exhaust Vent) are also avaUable to monitor noble gas releases as edl as pmticulatcs and iodmc.
Coutslutncut Effluent 48 C
Noble Gas at Pen,etc.
2 18-6 to 1E-2 )tCJ/cc pcs no SS rel.
no
'ce item ft47. These monitors are considered to provide, adequate monitoring ofall crcdiblc.
releases.
49 D
RHR Systctn Floe 2
0 - 110
% design ycs no partial rcl.
no no
'ce item it 14, RG&E'Q7e A variable, RIIR Heat Excbanger D
Outlet Tem eratore 2
40 'F - 350 'F pcs n o partial rel.
n o oo n.a.
7FA27 3
50 4F - 400'F no no SS TSC no ao
'T0627 NRC SER dared 12/4/Ã found thc range provided acceptable.
TYPE VARIABLE Attachment 3
Table 1
Comparison of Glnua Post Accident Iustrumenlatlou tu Regulatory Guhle 1.97, Revlslon 3 Crlterla C. R.
RECORDER CAT.
RANGE EEQ SEISMIC QA I'.S.
IND.
CIIART COMP COMMENTS Page 11 o'f 20 Accumulator Tank 51 D
Level 2
10%-90%
yes n o partial u.p.
no uo n.a.
LT-934 (l~p 8)
LT-935 (Loop A)
LT-938 (Loop 8)
LT-939 (I~p 8) 3 k7 inches from nominal no 3
k7 inches from nominal no 3
k7 inches from nominal no 3
X7 inches from nominal no no no no no SS 1C Ll-934 no SS IC LI-935 no SS IB Ll-938 no SS 18 LI-939 no no NRC SER dated 12/4/90 founi the no instrumentation provided acceptable. The no catagory 3 designation is consistent with no RG&E's catagory determination philosophy.
Accumulator Tank 52 D
Pressure n.a.
PI'-936 {Loop8)
Fl'-937 (Loop A)
Pl'-940 (Loop A)
PT-941 (I.oop 8) 2 0 - 750 pslg 3
0- 800 psig
,3 0 - 800 psig 3
0- 800 psig 3
0- 800 psig yes u o partial n.p.
u o no no SS IC Pl-936 no no no.
SS IC Pl-937 no no no SS 18 Pl-940 no no no SS 18 Pl-941 no no no NRC SER dated 12/4/90 deferred resolution of no these deviations to generic staff review ofthis no issue. The catagory 3 designation is consistent no with RG&,E's catagory determination philosophy.
Accumulator Iso.
53 D
Valve Position 2
open I closed yes n o partial n.p.
n o no n.a.
MOV-841 (Loop A)
MOV-865 {I.oop8) 3 open/closed 3
open/closed no ycs SS ADC ycs no no Valves are locked open and dc<ncrgized.
no.
ycs SS HDC yes no no NRC SER dated 12/4/90 found the instrumentation provided acceptable.
Boric Acid Charging 54 D
Flow 2
0 - 110
% design yes no partial rel.
no no n.a.
FT-128 2
0-75 gpm mild no SS ID I:1-1288 no H)I28 NRC SER dated 4/14/86 found the instrumentation provided acceptable lllgh Pressure 55 D
Injection (Sl)
Flow 2
=0 - 110
% design yes n o partial rel.
no uo e see item N17, RG&E Type A variable.
¹ TYPE VARIABLE Attachment 3
Table I Comparison of Glnna Post Accident instrumentatlon to Regulatory Guide 1.97, Revlslon 3 Criteria C.R.
RECORDER CAT.
RANCE EEQ SEISMIC QA P.S.
IND.
ClIART COMP COMMENTS Page l2 of 2tt I.ow Pressure 56 D
Infection (R}ilt) Flow 2
O - llo % design yes u o partial rel.
no
~ sce item ¹14, RG&E Type A variable.
57 D
R WST.I.evel 2
top to bottom y es n o par tlal rel.
n o no
~ see item ¹16, RG&E Type A variable.
58 D
RCP Status 3
motor current no no comm.
n.p.
no D
4.16kV Bus ammctcrs 3
0- 1200 A and IICt'rcakcr status lights no no S S n.a.
ycs no ycs Pressurizer PORVs 59 D
and Safeties Position 2
closed I not closed yes no partial rel.
no no A
D ZT434 (Safety Valve) 2 open - close (inchcs)
ZT-435 (Safety Valve) 2 open - close (inchcs)
TE436.TE437 (Safeties) 3'~ O'F -400'F ycs ycs SS lA yes no no y'es yes SS 1 A yes no no no ycs SS IA
'1'1-436 no no
~ Pressurizer PORVs position indication is considered a Type Avariable see item ¹10.
"The RTD's downstream ef these valves,
'I%436 and 1%437, are available in the control room and are considered backup indication'of valve position.
60 D
Pressurizer Level 1
top to bottom yes yes full IE yes Plant Specific
~ see item ¹9, RG&E Type Avariable.
note: level indication docs no'. cover the hemispherical top and bottom portions of the pressurizer.
¹ TYPE VARIABI.E Attachment 3
Table 1
Comparison of Glnna Post Accident Instrumentation to Regulatory Guide 1.97, Revlslon 3 Crlterla C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 13 of 20 Pressurizer Ileaters 61 Status 2
electric current yes n o partial rel.
no no D
control bank breaker status lights backup bank breaker status lights 480V Bus voltage and kWdemand 2
closed/auto/on 2
closed/auto/on 2
0- 1500 kW mild no mild no mihl no SS n.a.
ycs no yes SS ADC yes no no NRC SER dated 12/4/90 found the instrumentation provided acceptable.
SS BDC yes no no Pressurizer Relief 62 D
(Quench)
Tank Level 3
top to bottom n o n o comm.
n.p.
n o no D
LTM2 3
0- 100%
no no SS 1B LIM2 no L0442 Pressurizer Relief 63 D
(Quench)
Tunk Temp.
3 50 'F - 750 'F no no comm.
np.
no no D
TE439 3
(50 OF -400 oF) no no SS lA Tl-439 no T0439 NRC SER dated 12/4/90 found the instrument range acceptable.
Pressurizer Relief 64 D
(Quench)
Tank Press.
3 0 pslg to design no no comm.
n p.
no no D
0- 150 psig no no SS 1B PI440A no P0440 rupture disk setpoint is 100 psig.
I I-440B Steam Generator Wtde 65 D
Range Level A
hvo per generator required for two loop 1
tube sht - separators
- yes, yes fult IE yes Ptant Speclflc huts IP a see item ¹18, RGAE Type A variable.
¹ TYPE VARIAIILE Attachment 3
Table 1
Comparison of Glnna Post Accident Iustrumentatlon to Regulatory Guide 1.97, Revlslon 3 Crlterla C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA I'.S.
IND.
CllART COMP COMMENTS Page l4 of 20 Steam Generator 66 D
Pressure 2
atm. - 20%
o safety yes no partial rel.
no no
>> see item ¹20, RG&E Type A variable.
Main Steam Flow (or D
S(1 safety valve pos.)
2 0 - 110
% design yes no partial rel.
no no
>> sce item ¹21, RG&E Type A variable.
68 D
Main Feedwater Plow 3
0 - 110
% design no no comm.
n.p.
no no D
FT466 (SG A)
~
FT467 (SG A)
Fl'476 (SG B)
Fl'477 (SG B)
Ff-500 (SG A)
FT-503 (SG B) 3 0- 3.8E6 pph no no 3
0 38E6 pph no no 3
0 - 3.8E6 pph 'o no 3
0 - 3.8E6 pph no no 3
0- 3.8E6 pph no no 3
0 - 3.8E6 pph no no SS IA/IC FW66 SS IA/IC FI467 SS IA/IC F1476 SS IA/IC F1477 SS IA/IC FI-500 S S IA/IC Fl-503 ycs>>
F0466>> Recorders FR-465 (SG A) and FR475 (SG yes':0467 B) record median flowof the 3 channels.
yes'0476 Main Feedwater Flow transmitters receive yes>>
I:0477 power fiam the Digital Feedviater Control yes>>
F0500 System (ADFCS). Power for the system is yes'0503 auctioncered from buses IAand IC.
Auxttlary Feedwater 69 D
Flow 2
0 - 110
% design yes no partial rel.
no no
>> see item ¹I, RG&E Type A variable.
Condensate Storage 70 D
Tank Level A
I Plant Speclflc y es y es full IE yes Plant Speclflc
->>>>>> see item ¹7, RG&E Type A. variable.
¹ TYPE VARIADI.E Attachment 3
Table I Comparison ot Glnna Post Accident Instrumentatlon to Regulatory Guhle 1.97, Revlslon 3 Crlterla C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA l'.S.
IND-CIIART COMP COMMENTS Page 15 of 20 Containment Spray 71 D
Flow 2
0 - 110 % design yes no partial ret.
no n.a..
none no
~ indirect indicadon ofContainmcnt Spray flow is available using Sl flowand RHR flow. NRC SER dated 12/4/90 found this acceptable.
Containment Fan 72 D
Hest Removal n.a.
none 2
Plant Specific y es n o partial rel.
n o no
~ indirect indication ofContr inment Fan heat removal is available using containmcnt air temperature, sump temperature and containment pressure. NRC SER dated 12/4/90 found this acceptable.
Containment Alr 73 D
Temperature 2
40 'F - 400 'F yes n o psrtlst rel.
no no D
TE-6031 (clcv. 245'")
TE-6035 (clcv. 26I'")
TE.6036 (clcv. 261'")
TE4037 (elcv. 261'")
TE-6038 (elcv. 261'")
TE-6045 (elcv. 286'4")
2 04F - 300 oF 2
0 'F - 300 'F 2
O'-300 F 2
04F -300'F 2
O'F - 300'F 2
O'F - 300'F (yes)
(ycs)
(ycs)
(ycs)
(yes)
(ycs)
(ycs)
(yes)
(yes)
(yes)
(yes)
(ycs)
~~
~~
no SS
's no SS
~~
no yes~
yes~
yes+
yes+
yes~
yes~
ycs 6 Environmentally qualified Containment Air ycs Tcmpemture RTD's are being installed during yes the 1992 Refueling outage. NRC SER dated yes 12/4/90 found the range deviation to be yes acceptable. s recorded at ILRTpanel yes s'E supply from MCC 1D (B train)
Containment Sump 74 D
Tem erature 2
50'F-250'F yes n o partial
.rel.
no n.a.
TE490 A/B (Sump A) 2 0 'F-360'F TE491 A/B (A.3'above 2
O'F - 360'F basement floor) yes yes SR IA/IC no ycs ycs SR IA/1C no no llo yes TE490A/B and TE491A/B are dual element ycs RTD's. The 'A'lements are powered from bus lAand the 'B'lements are powered from bus 1C. Each element is available on the PPCS as a separate point.
Reactor Water D
Makeup Flow (CVCS) 2 0 - 110
% design yes no partial rel.
no no n.a.
Fl'-111 2
5-75 gpm (0- 100%)
mild no SS 1D no FR-110 no NRC SER dated 12/4/90 found the instrument range acceptable.
tt TYPE VARIABLE Attacbment 3
Table 1
Comparison of Glnna I'ost Accident Instrumentatlon to Regulatory Guide 1.97, Revlslon 3 Crlterla C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CIIART COMP COMMENTS
'Page 16 of 20 76 D
I.etdown Flow (CVCS) 2 0 - 110
% design yes no partial rel.
no no n.a.
FT-134 2
0- 100gpm (0- 100%)
mild no SS ID FI-134 no F0134 Volume Control Tank 77 D
Level 2
top to bottom yes n o partial rel.
no no n.a.
LT-112 2
0- 100%
mild no SS IB LI-112 no L0112 CCW Temperature to 78 D
ESF System 2
40 'F - 200 'F y es n o partial rel.
no no n.a.
TE-621 (Component 2
0'F - 225 'F Cooling Water heat exchanger tcmpemture) mild no SS lB Tl-621 no
'19621 NRC SER dated 12/4/90 found thc instrumentation provided to be acceptable.
System 2
40 oF - 200 'F yes n o partial rel.
no no n.a.
FI'419 (Component Cooling Water System flow) 2 0- 7000 gpm mild no SS IC no no F0619 11te CCW System is prealigned with flows to various ESF components manually adjusted using local flow indicating switches. RG 1.97 states that the purpose oftl is variable is to monitor operation. 'IIte instrumentation provtded meets the mtent.
Ht Level Radloacttve 80 D
Llquld Tank Level 3
top to bottom no no comm.
n.p.
no no' LT-1001 (Waste Drain Tank)
LT-1003 (Reactor Coolant Drain Tank) 3 0- 100%
3
~0-100%
no: no SS
~
no no no
.SS
~
no no no
~ Normally fed ftam480 Vbus 14 (Gain A) with a manual backup to 480 V bus 16 (Ttain no L1003
¹ TYPE VARIABLE Attacbment 3
Table 1
Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revlslon 3 Crlterla C. R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CHART COMP COMMENTS Page 17 of 20 81 D
Radloactlve Gas Holdup Tank Pressure 3
0 - 150 % design n o n o comm.
n.p.
n o no n.a.
PT-1036 gank I)
Ff-1037 (Tank 2)
PT-1038 (Tank 3)
Ff-1039 g ank 4) 3 0- 150psig (0- 100%)
3 0- 150psig (0- 100%)
3 0- 150psig (0- 100%)
3 0-150psig (0- 100%)
no no no
.no no no no no SS t
no SS t
no SS t
no SS t
no no no no no no Design ofeach tank, and its safety valve no sctpoint is 150 psig. Noma) radgas pump no operating pressure is <100 psig. NRC SER no dated I/90 found this range deviation acceptable. t Normally fed from 480 V bus 14 with a manual backup to 480 V bus 16:
82 D
Emerg.Ventllatlon Damper 'osltlon 2
open / closed yes n o partial rel.
n o no Zf-7970 (mini-purge)
Zf-7971 (mini-purge)
Zf-7445 (mini-purge)
Zf-7478 (mini-purge) 3 3
3 3
open/closed open/closed open/ closed open / closed no ycs SS ADC yes no no ycs.
S S ADC yes no no ycs SS ADC yes no no yes S S ADC yes no no Mini-purge valves arc locked closed and only no openned for containment prcssure control.
no
'Iliese valves are in their safety related position no prior to any adverse conditions and do not change position throughout any accident.
1herefore EQ is not deemed necessary.
83 D
Stdby power / Energy Imp. to Safety Status
~
2 Plant Speclflc yes n o partial rel.
n o no D
EDG A,B: V,kW,A 3
125VDCA,B: V,A 3
'T-2023 (Instrument Air) 3 PT-1066 (Nitrogen Gas) 3 Ff455 (PORV, Sl Acc) 2 Fl'456 (PORV, Sl Acc) 2 0-500V,0-3000A,0-2MW mild 0-150 V, 0-50 A mild 0- 160 psig mild 0 - 150 psig mild 0- 1000 psig mild 0- 1000 psig mild no no no no no no SS SS NS NS SS SS n.a.
ycs n.a.
yes PI-2023 no IB PI455 IA PI456 no no no no no no yes yes no no no Containment Hlgb Radlatlon Monitor 1
I
- 1E7 R/hr yes yes full IE yes Plant Speclflc t
t see item ¹4, RG&E Type A variable.
85 E
Rad. Exposure Rate-Access rqd. areas 3
1E-I - IE4 R/hr Various Microprocessor 3
0.1 - 1E7 mR/hr based monitors located, and qualified to satisfy NUREG4654 no no comm.
n.p.
no no no no SS various yes yes yes
TYPE VARIABLE Attachment 3
Table I Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revlslon 3 Crlterla C.R ~
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S.
IND.
CIIART COMP COMMENTS Page Ig of 20 Airborne Rad Release 86 E
Noble Gas and Flow 2
lE lES IrCI/cc yes no partial rel.
no C
no
~ see item //47, RGAE Type C variable Airborne Rad Release 87 E
Part.
and Ilalogens 3
IE IE2 IrCI/cc no no comm.
n.p.
no il 0 E
R-12A (Cont. Vent) 3 IE-5-10IICi/cc halogcns, IE-6-1ltCi/cc R-14 A (Plant Exh. Vent) 3 particulate 5E-5-50ltCi/cc
- halogcns, 2.5E-5-25ItCi/cc part.
no no no SR 'es ycs R12A
~ SPING Radiation monitors are powered from a dedicated supply 6om MCC D (Safety no SR yes ycs R14A Related).
Airborne Radio. and 88 E
Part (portable samp) 3 IE 9 - IE 3 IrCI/cc no no comm.
n p.
no no E
Various fixed and portable 3
IE-12-IE-3 pCi/cc samplers (Aliquotor diluted sample) no no SS n.a.
no no no Plant and Environ.
89 E
Radlatlon (portable) 3 IE IE4 R(rad)/hr n o n o comm.. n.p.
n o'o beta radlatlons and photons E
Various portable instrumentation 3
lE-'6-1E3 R/hr gamma no no SS n.a.
no no no IE IE3 R/hr beta Plant and Environ.
E Radloactlvlty (port,)
3 Isotopic analysis n o n o comm.
n.p.
n o no E
Multichannel Gamma Ray Spectrometer 3
lE 10 pCi no no SS n.a.
no
'o.
no
tt TYPE VARIABLE Attachment 3
Table I Comparison of Glnna Post Accident Instrumentatlon to Regulatory Guide 1.97, Revlslon 3 Crlterla C.R.
RECORDER CAT.
RANGE EEQ SEISMIC QA P.S-IND.
CHART COMP COMMENTS Page 19 of 20 91 E
Wtnd I)lrectlou 3
0-360O no no comm.
np.
no no E
wind direction (met tower) 3 0-360'o no SS>>
no RK-32 WD033 ~ the weather tower currently receives power WD150 directly via an offsite supply.
WD250 92 E
Wind Speed 3
0-67 mph no no comm.
n.p.
no no E
wind speed at 33, 150, 3
0- 100 mph 250 ftelevations (met tower) no no SS>>
no RK-32 WS033>> the weather tower currently receives power WS150 directly via an offsite supply.
WS250 Estlmatlon of 93 E
Atmospheric Stab.
3 based on vert. AT n o n o comm.
n.p.
no.
no E
RTD's at 33, 150,250 ft 3 20>>F betwccn each no no SS elcvations (mct tower) clcvation yes>>'o WDTI >> the weather tower cutrentl) receives power WDT2 directly via an offsite s'upply.
>>>> Tcmpcraturcs at each elevation are displayed in the control room.
Accident Sampling:
gross actlvlty, gamma
- spectrum, 94 E
various
- no no comm.
n.p.
no no
gross activity (grab samp) 3 1 - IE6pCi/cc (dilution) gamma spectrum 3
mutichannel analyscr boron content 3
50 - 6000 ppm chloride content 3
5 ppb-100 ppm dissolved hydrogen, 3
10- 2000 cc/Kg dissolvcdoxygcn,pH 3,3 0.1-20ppm, 1-13pH no no no no no no,no no SS no SS no SS no SS no SS no,no SS,SS no no no no no no, no no no no no no no, no no no no no no no, no
>> 'Ibe PASS panel is powered from 480 V bus 13 (non SR) via panel SB14. NRC review of the PASS capability was documented under NUREG4737 Item II.B.3 (SER dated 4/14/84). NRC SER dated 12/4/90 concludes that the minor range dcvhtions are acceptable.
Accident Sampling:
- content, oxygen
- content, 95 E
Contatnment Alr 3
various n o n o comm.
u.p.
no no amma s ectrnm E
Hydrogen content Oxygen content Gamma Spectrum 3
0- 10% (PASS) no 3
0- 30% (PASS) no 3
multichannel analysis no no SS n.a.
no no no Hydrogen concentration is also avaihble using no SS n.a.
no no no the installed Type AHydmgcn Monitors, sce no SS n.a.
no no "no
. item N5.
Page 20 of 20 httadmont 3 Table 1
Comparison of Ginna Post Eccident Instrweeatatioa to Regulstary Guide 1.97, Revision 3 Criteria Holes Radioactivit Concentration or Radiation Level in Circulatin Prima Coolant (Isotopic hnalysis)
The original design basis for implaxntation of HUREG-0737 Topic II.B.3, involves sampling requirements to perform a radiological analysis within a three hour time period for "certain radionuclides in the reactor coolant...".
The HVREG-0737 Clarification, dated October 31, 1980, (2)(d), states nhlternatively, have inline monitoring capabilities to perform ail or part of the above analysis".
Ginna's response involved the selection of semi-autcmated manual dilution techniques involving sample witldrawl and preparation of the sample aliquot by the Post-hccident Sampling System, not a inUne aanitoring capability.
The remote~ual sampling and dilution capabilities of the existing installed equipaent are equivalent to Category 3, Type C attributes.
The Ginna Post.-Accident Sampling System (PhSS) is equip@4 with reaate-manual abilities to acquire a Reactor Coolant System (RCS) sample, then manipulate the saaqle by diluting it approximately 1000:1.
The diiutant may than be manually delivered to either of two d1verse counting facilities at Ginna Station for multichannel spectrometer isotopic analyses.
The PLSS panel is utilized by Health Physics technicians at least once per week to produce routine proceduralized analyses when the unit is on-line.
Regulatory Guide 1.97 guidance for radiation concentration determinations states that Category 1, Type C attributes apply to this amasurvcent variable with the purpose stated to'e detection of breach (Fuel Cladding Topic).
Fuel cladding breach detection is not within tbe Ginna licensing basis but is adcnowledged to be a concern during Functional Restoration activities.
Functional restoration activity beyond the Ginna licensing basis.
Mo EOP activity involved with P~ign basis DBh occurrences requires that the radiation concentration determination in RCS be performed, and there's no consequent operator action tequiamant,.