Text

Rev 1 to Oyster Creek Response to NRC Reg Guide 1.97 (Rev 2)
	ML20137B516
Person / Time
Site:	Oyster Creek
Issue date:	06/13/1984
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20137B464	List: ML20137B460; ML20137B516;
References
	RTR-REGGD-01.097, RTR-REGGD-1.097 GL-82-33, TDR-528, TDR-528-R01, TDR-528-R1, NUDOCS 8511260287
	Download: ML20137B516 (70)
	v • d • e

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i AttIchment Oyster Creek Response to USNRC Regulatory Guide 1.97 (Rev.- 2)

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T_ABLE OF CONTENTS l

1 Paragraph p,g, l

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1. Introduction 7

2. Methods 4

3.. Results 4

14. Conclusions 5

5. Recor.raendations 5

6. References 5

7. Tables 5

8. Attachments 1-26

9. Table I 1-24

10. Table II 1-13

11. Table III

TDR 528 Rev. 1 Page 3 of 70 I. INTRODUCTION USNRC Regulatory Guide 1.97, Revision 2, was issued in December, 1980. The intent of Regulation Guide 1.97 is to ensure that all light water reactors are properly instrumented to assure proper responses during and following an accident. Regulatory Guide 1.97 provides methods which are acceptable to the NRC staff to comply with the comissions requirements for instrumentation necessary to monitor and assess plant conditions during and following an accident.

In addition, Generic Intter 82-33 required that all utilities provide a schedule for implementing Regulatory Guide 1.97. On April 15, 1983, GPU Nuclear advised the NRC that GPU would perform a plant specific study for Oyster Creek and submit the results of this study, including a schedule of implementation in May 1984.

Tne purpose of this report is to provide the following information for Oyster Creek Nuclear Generating Station (OCNGS):

- Specify the minimum parameter set to meet the intent of R.G.

1.97, Revision 2.

- Determine the status of the existing instrumentation against the R. G. 1.97 design and qualification requirements.

- Provide justification for the variables that do not comply witn the requirements of R. G. 1.97 Dut are considered adequate for OCNGS.

II. METHODS A. NRC Position Tne NRC in R. G. 1.97, Revision 2, Table I identified a minimum list of "B", "C", "D" and "E" type parameters for light water reactors and their required ranges. Type "A" variaoles were not specified because they will depend on the specified planned manual operator actions required during Reactor Accidents. The NRC has stated that Type "A" variables would be determined on a p] ant specific basis.

B. BWROG Position on R. G. 1.97, Revision 2 Tne recommendations of the BWROG titled "BWR Owners Group Position on NRC Regulatory Guide 1.97, Revision 2" can be found in a BWROG report by the same title. Tne EWROG identified five variables as Type "A" and proposed six additional variables as potential Type "A". Also, the BWROG stated its position with regard to Types "B", "C", "D", and "E" variaDies and design categories as identified in R.G. 1.97, Table I.

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e TDR 528 Rev._1 Page 4 of 70 C. GPUN Position GPUN concurs with the reconsnendations of the BWROG except as noted in Table I of this report. Also, in the selection of Type "A" variables, GPUN did not limit the selection process to Design Basis Accident Events only because:

a) Scenarios that could lead to core damage or radiation release to the public, may not have been considered as a basis in the analysis included in the Facility Design and Safety Analysis Report, (i.e., the TMI-II Maren 28, 1979 event); and therefore, could be e erlooked.

b) The parameter selection tecnnique employed in R. G. 1.97 was a critical safety function (i.e., reactivity, core cooling, reactor coolant system integrity, and containment integrity) approach and dces not lend itself to an event oriented approacn.

c) This critical function approach is also used in development of tne Emergency Operating Procedures (EOPs) and their entry conditions. This would also preclude using an Event Oriented approacn.in determining what "specified manually controlled actions" are required in the EOPs for " safety systems to accomplish their safety function".

d) The BWROG also used symptom oriented EOPs and critical safety function approach in the formulation of their position on R. G.

1.97. Again, an event oriented approach would be inconsistent with existing work and any results would be suspect, e) A review of the existing emergency operating procedures (500's)

. for any specified manual actions proved futile. Most procedures simply state " ensure all automatic functions have taken place" and assume most everything functions properly. In the case of the refueling accident DBA, no specific procedure currently exists. Symptom Based Emergency Operating Procedures were then used as a source of planned manual actions.

Therefore, a symptom oriented critical safety function approach was used in con] unction with the EOPs in selecting Type "A" variables,

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TDR 528 Rev. 1 page 5 of 70

~D. Definitions Tne following definitions of Type variables and Categories are taken from R. G. 1.97.

1) Type "A" "Those variaoles to be monitored that provide the primary information required to permit the control Room Operator to take the specified manually controlled actions for which no automatic control is provided and that are required for safety systems to acconplish their safety function for design basis accident events." R. G. 1.97 calls these variables plant specific and requires plants to specify them as needed.

2) Type "B" "Those indications that provide information to indicate wnetner plant safety functions are being accomplished.

3) Type "C" "Tnoce variables that provide information to indicate the potential for being breached or the actual breach of the barriers to fission product release, i.e., fuel cladding, primary coolant pressure boundary, and containment."

4) Type "D" "Those variaoles tnat provide information to indicate the operation of individual safety systems and other systems important to safety.".

5) Type "E" "Those variables to be monitored as required for use in determining the magnitude of the release of radioactive materials and in continually assessing such releases."

6) Category 1 "Provides the most stringent requirements and is intended for key variables" (i.e., Class IE, seismic, single failure, and Type "A" and "B" key variables).

7) Category 2 "Provides less stringent requirements and generally applies to instrumentation designed for indicating system operating status." (Type "D" and "E" key variables).

8)- Category 3 "High-quality off the shelf instrumentation."

(Backup and diagnostic information).

These definitions provide tne functional requirements for tne design and qualification criteria for instruments identified in this report.

r TDR 528 Rev. 1 Page 6 of 70 III. RESULTS The results of this report 'are sumarized in Taoles I, II, and III.

A. Table I - Proposed Parameter Set for Oyster Creek Table I lists the variables and. categories proposed by R. G. 1.97 and the BWROG's and GPUN's position on these variables. Table I also contains the BWROG's recomended and proposed Type "A" variables. Justification for inclusion or exception to the R. G.1.97 or BWROG's recomendation are contained in Taole I as required.

The basis for developing Table I of this report was R. G.1.97, Revision 2, Supplement I of NUREG 0737 (Generic Iatter.

82-33) and the Oyster Creek Emergency Operating Procedures.

B. Table II - Status of Minimum Parameter Set for Oyster Creek Table II provides a minimum parameter set for Oyster Creek based on R.G.1.97, the coments of the BWROG and a detailed review of the Oyster Creek Control Room in light of emergency procedure requirements. Table II also provides tne status of these parameters Dased on the requirements listed in R.G. 1.97, Taole I.'

C. Table III - Actions Required to Satisfy R.G. 1.97 Requirements for OCNGS Minimum Parameter Set Table III addresses the deficiencies identified in Table II.

Justification for variables that are not in strict conpliance with R.G. 1.97, but for which GPUN does not feel upgrading is required,-

is also presented in Table III.

In addition, Table III provides justification for those variaoles which satisfy R. G. 1.97 requirements with regard to performance and environmental qualifications out do not necessarily satisfy R. G. 1.97 regarding Quality Assurance and seismic requirements.

IV. CONCLUSION The conclusion of tnis report is the minimum parameter set identified in Table,II and the status of compliance for each parameter identified therein. Also, it is concluded tnat several of these parameters need upgrading while others are to be accepted as is. 'Ihese items are identified and discussed in Table III.

i.

TDR 528 Rev. 1 Page 7 of 70 V.. RECOMMENDATIONS It is recoittnended that the parameter instrumentation requiring upgrading identified in Table III be performed.

VI. REFERENCES

1. R. G. 1.97, Revision 2, Decemoer, 1980.

2. BWROG Response to R. G. 1.97, Revision 2, December, 1980.

3. USNRC Regulatory Guide 0737.

4. USNRC Regulatory Guide 0696.

-VII. TABLES A) Table I - Proposed Parameter Set for Oyster Creek B) Taole II - Status of Minimum Parameter Set for Oyster Creek C) Table III - Actions Required to Satisfy R.G. 1.97 Requiremenets for OCtGS Minimum Parameter Set for Minimum Parameter Set VIII. NITACHMENTS A) BWROG Position on NRC Regulatory Guide 1.97, Revision 2, July, 1982.

TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Y = Yes (Implement)

N = No (Do Not Implement)

P = Proposed Reconvaended By f4RC BWROG GPUN Y/N Cat Y/N Cat Y/N Cat Justification Parameter Description

- - Y 1 Y 1 a) Depressurize the reactor and monitor a A-1 RPV Pressure safe cooldown rate.

b) Operation of the Isolation Condenser to maintain pressure in the E0P pressure control section. ,

c) Detection and correction of a cycling EMRV.

d) Verification that pressure is less than 285 psig prior to opening. core spray parallel valves.

e) Tak? manual pressure control if safety systems fail.

The safety functions involved are:

a) Adequate core cooling.

b) Reactor coolant system integrity.

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9 TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Reconmended By NRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification

- - Y l Y 1 Hanual operator actions are:

A-2 RPV Water Level a) Restore and maintain water level:

1) Throttle core spray to prevent flooding the vessel.

2) Take manual actions if safety systens do not function properly.

3) Ensure level is low enough to prevent severe water hanner prior to operation of isolation condensers or EMRVs.

4) Needed to override ADS until reactor level reaches TAF in the E0Ps.

The safety functions are: ,

a) Adequate core cooling.

b) Reactor coolant system integrity.

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i TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Reconmended By HRC BWROG GPUN Y/N Cat Y/N Cat Y/N Cat Justification Parameter Description Y 1 Torus water temperature is~an indication of:

A-3 Torus Water Temperature - -

Y 1 a) Exceeding design temperature limits.

b) Adequate heat absorption capability in the torus, c) ECCS pump net positive suction head (NPSH).

As well as being an E0P entry condition of torus water temperature is an action level to:

a) Initiate torus cooling.

b) Scram the reactor or initiate ifquid poison during an ATWS.

c) Emergency depressurization of the reactor to stay within the heat capacity temperature limit.

d) Close a stuck open EHRV.

Torus water temperature measurement is required by NUREG 0783.

The safety functions are: 2? y d E ? ."

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TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Recommended By HRC BWROG GPUN Parameter Description Y/H Cat Y/N Cat Y/N Cat Justification A-4 Torus Water Level - -

Y 1 Y 1 Hanual operator actions are:

a) Maintaining torus level below the torus load limit curve or depressurize the reactor to below the load limit in the E0Ps.

b) Add water as necessary to ensure ECCS equipment has adequate NPSH.

c) Limit an increasing level to ensure an adequate torus vent path.

Safety functions are:

a) Containment integrity, b) Adequate core cooling.

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TABLE I PROPOSED PARAt1ETER SET FOR OYSTER CREEK Recor.nended By NRC BWROG GPUN Justification d' Parameter Description Y/N Cat Y/N Cat Y/N Cat Drywell Pressure - - Y 1 Y 1 ilanual operator actions are:

A-5 a) Start containment spray since this requires a coincident 10-10 reactor water level signal for automatic initiation.or

- if a failure to auto start occurs.

Safety functions are:

a) Prinary containment integrity.

b) Reactor coolant integrity.

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t TABLE I PROPOSED PARAt1ETER SET FOR OYSTER CREEK Reconnended By HRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification Drywell Temperature - -

P - Y l Drywell temperature is a direct indication of A-6 approaching design temperature limits which could. lead to violation of the safety function of. preserving primary containment integrity.

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Also, drywell temperature is an entry condition to the E0Ps and an action level'to initiate contsinment spray and scram the reactor.

Manual operator actions are:-

a) Scram reactor.

b) Initiate containment spray, c) Comnence P,eactor Shutdown. ~

Safety functions are: '

a) Reactor coolant integrity. .

b) Containment integrity, o _

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TABLE I PROPOSED PARAHETER SET FOR OYSTER CREEK Recocsaended By NRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification A-7 Torus Pressure - -

P - Y l Torus pressure is a direct indication of approaching the torus design pressure limits and is paramont in preserving primary containment integrity. Also, torus pressure is an action level in the E0Ps.

Manual operator actions are:

a) Initiate torus spray to prevent exceeding the torus design pressure limit.

b) Energency depressurization prior to exceeding torus pressure limit (Figure G in E0Ps).

c) RPV flooding is required prior to i

exceeding torus pressure limit (Figure H in E0Ps).

d) Drywell spray initiation is required prior to exceeding torus pressure limit j

(Figure I in E0Ps).

e) Venting of the drywell is required in Figure I if the E0Ps is exceeded.

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s TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Recommended By NRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification Safety functions are:

l a) Adequate core cooling.

l b) Primary containment integrity.

The BWROG has stated that the drywell pressure could be used to infer torus pressure. The E0Ps specifically deal with torus pressure.

If drywell pressure is used, a correction factor based on torus level is required to correct for downcomer subnergence. This manual correction would he time-consuning and l cumbersome during emergency conditions and i could lend to erroneous results and operator actions. .

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i TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Recommended By NRC- BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification A-8 Drywell Combustible Gas - -

P - Y l Manual actions are:

Concentration (02 , H2) a) Shift to an alternate mode of core cooling due apparent cladding failure (i.e.

2r/ water reaction).

b) If hydrogen exceeds explosive linits, institute hydrogen control procedures.

Safety functions are:

a) Adequate core cooling.

b) Primary containment integrity.

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TABLE I PROPOSED PARM1ETER SET FOR OYSTER CREEK Recommended By HRC BWROG GPUN Parameter Description Y/N Cat Y/fl Cat Y/N Cat Justification-A-9 Condensate Storage - -

P -

N -

Only proposed for those plants with HPCI or RCIC systems with automatic suction transfer ~-

(i.e. from CST to torus). These systems do not exist at Oyster Creek (See D-2). See BWROG discussion in Appendix A. Page 12.

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s TABLE I PROPOSED PARAttETER SET FOR OYSTER CREEK Recommended By NRC BUROG GPUN Y/N Cat Y/N Cat Y/N Cat Justification Parameter Description P - N - The only " safety related" loads that would be Emergency Diesel - -

A-10 added to the EDG after a large accident are Generator Load RBCCW, service water, TBCCW fans and an air compressor. These loads are not needed immediately following a reactor accident.

Therefore, various ECCS loads may be secured (redundant core and containnent spray systems) leaving sufficient desired capacity.

See BWROG discussion in Appendix "A", Page 12, Reactor Building P - ti -

A-ll capacity for operator to pump reactor building Flood Level sump to torus does not exist and this is "an aid not the accomplishment of a safety function". General environmental monitoring (flood levels, temperatures, etc.) will be studied in a separate TDR.

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1 TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Recommended By NRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification B-1 Neutron Flux Y l Y 2 Y l GPUN concurs with the NRC on the identification of B-1.through B-10 as Type "B" variables except for B-4, BWR Core Thernocouples. See BWROG issue 3 for a discussion of B-4. Also, GPUN agrees with the BWROG on downgrading B-8, Drywell Sump Level, to a Category 3. See BHROG issue H for a discussion. (BWROG report is enclosed as

- Appendix A).

B-2 Control Rod Position Y 3 Y 3 Y 3 See B-1.

B-3 RCS Boron Concentration Y 3 Y 3 Y 3 See B-1.

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TABLE I PROPOSED PARAt1ETER SET FOR OYSTER CREEK Reconsnended By NRC BWROG GPUN Pararaeter Description Y/N Cat Y/N Cat Y/fl. Cat Justification B-4 RPV Water Level Y l Y 1 Y 1 See B-1.

B-5 BWR Core Thermocouples Y l N -

N -

See B-1.

B-6 RPV Pressure Y l Y 1 Y l See B-1.

B-7 Drpell Pressure Y l Y 1 Y l See B-1.

B-8 Drpell Surap Level Y 1 Y 3 Y 3 See B-1.

B-9 Drpell Pressure Y l Y l Y l See B-1.

B-10 Drpell Isolation Valve Y l Y l Y l See B-1.

i B-ll Drpell Temperature - - - -

Y 1 See A-6.

B-12 Torus Pressure - - - -

Y l See A-7.

B-13 Torus Water Teraperature - - - -

Y 1 See A-3.

B-14 Torus Water Level - - - -

Y l See A-4.

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TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Recommended By NRC BWROG GPUN

. Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification B-15 Drywell Water Level - - - -

Y 2 Drywell level (B-15) is an extension of B-14.

above and is needed for assurance of adequate core cooling when drywell flooding is required per the E0Ps. Although torus pressure and drywell pressures could be used to estimate level, accuracy would be very limited and the drywell pressure tap is below the maximum flood level.

B-16 Reactor Building - - - -

Y 3 Reactor building dp is needed to assess the Diff. Pressure integrity of the secondary containment.

B-17 Drywell Reference - - - -

Y l Provides indication as to whether or not the Leg Temperature core is being covered during steady state or accident conditions.

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s TABLE I PROPOSED PARAt1ETER SET FOR OYSTER CREEK Recommended By NRC BWROG GPUN Y/H Cat Y/N Cat- Y/H Cat Justification Parameter Description Y l N -

H - BWROG Issue 5 C-1 Radioactivity Conc. or Radiation Level in Primary Coolant 3 Y 3 Y 3 C-2 Analysis or. Reactor Y Coolant (Grab Sample) l N - N - BWROG Appendix "A" C-3 BWR Core Thermocouples Y Y l Y l Y l C-4 RPV Pressure 3 Y 3 Y 3 C-5 Drywell Area Radiation Y BWROG Issue 4. Use alarm, leak rate indicator, C-6 Drywell Sump and Equipment Y l Y 3 Y 3 flow integrators and pump run time integrators.

Drain Tank Level Y 1 Y 1 Y l See A-4 C-7 Torus Water Level Y 1 Y 1 See A-5 C-8 Drywell Pressure Y 1 Y l Y 1 Y 1 See A-1 C-9 RPV Pressure Drywell Pressure Y l Y l Y l See A-5 C-10 2' 5' d -

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TABLE I PROPOSED PARAHETER SET FOR OYSTER CREEK Recoamended By NRC BWROG GPUN Parameter Description Y/H Cat Y/N Cat Y/N Cat Justification C-11 Drywell H2 Conc. Y l Y l Y. 1 See A-8 C-12 Drywell 02 Conc. Y -l Y l Y l See A-8 Containment Effluent Y 3 Y 3 Y 3 C-13 Radioactivity (Noble Gases)

C-14 Radiation Exposure Rate Y 2 11 -

N - See BWROG Issue 6. Not good indicator for detection of breach due to already high radiation levels.

C-15 Effluent Radioactivity Y 2 Y 2 Y 2 from Reactor and Turbine Building C-lG Drywell Temperature - - - - Y 1 See A-6 C-17 Torus Pressure - - - - Y l See A-7 C-18 Torus Temperature - - - - Y l See A-3 C-19 Drywell Isolation - - - - Y 2 indication.of direct breach of secondary and Rx Bldg. Vent Valve containment.

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TABLE I PROPOSED PARAETER SET FOR OYSTER CREEK Reconnended By HRC BWROG GPUti Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification Y 3 Y 3 Y 3 D-1 Main Feedwater Flow Condensate Storage Tank Y 3 Y 3 Y 3 D-2 Level Torus Spray Flow Y 2 N -

N - See BilROG Issue 1 D-3 Drywell Pressure Y 2 Y 2 Y 2 D-4 2 Y 2 Y 2 D-5 Torus Water Level Y Torus Water Temperature Y 2 Y 2 Y 2 D-6 2 Y 2 D-7 Drywell Teuperature Y 2 Y 2 N - See BWROG Issue 7. See D-19 (Cont. Spray Flow)

D-8 Drywell Spray Flow Y N -

2 N* N - *Not recommended if not part of plant design Main Streas Line D-9 Y Isolation Valve Leakage (BWROG)

Control System Pressure Safety Valve and EMRV Y 2 Y 2 Y 2 D-10 Position Flow or Pressure in Discharge Line

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TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Recoumended By NRC BWROG GPUN-Y/N Cat Y/N Cat Y/N Cat Justification Parameter Description Y 2 Y 2 Y 2 D-Il Isolation Condenser Shell-side Water Level Y 2 Y 2 Y 2 D-12 Isolation Condenser Isolation Valve Position Y 2 N - N - System not installed at Oyster Creek.

D-13 RCIC Flow Y 2 N -

N - System not installed at Oyster Creek.

D-14 HPCI Flow 2 Y 2 Y 2 D-15 Core Spray Flow Y Y 2 N - N - System not installed at Oyster Creek.

D-16 HPCI Flow 2 See BWROG Issue 9, Category 2. No action plan Y 2 Y 3 Y D-17 SLCS Flow until ATWS requirement is finalized. Use flow switch alarm and tank level.

2 Y 3 Y 3 See BUROG Issue 10.

D-18 SLCS Storage Tank Level Y 2 Y 2 Y 2 Primary indicator of the proper operation of D-19 Containment Spray System Y the containment spray system's function of delivering cooling water sprays to the drywell/ torus that is necessary for long-time decay heat removal during a LOCA.

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TABLE I PROPOSED PARAHETER SET FOR OYSTER CREEK Recommended By NRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justifi. cation D-20 Containment Spray Y 2 Y 2 Y 2 Primary indicator of the proper operation Heat Exchanger Outlet of the containment spray system's function Temperature of delivering cooling water sprays to the drywell/ torus that is necessary for long-time decay heat removal during a LOCA.

D-21 Emergency Service Water Y 2 Y 2 Y 2 Temperature to Containment Spray Heat Exchanger D-22 Emergency Service Water Y 2 Y 2 Y 2 Flow to Containment Spray High Radioactivity Y 3 Y 3 Y 3 In Radwaste Control Room only.

D-23 Tank Level D-24 Emergency Ventilation Y 2 Y 2 Y 2 j

Damper Position D-25 Status of Standby Power Y 2 Y 2 Y 2 and other Energy Sources Important to Safety s' 5' d i ? ".

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PROPOSED PARAMETER SET FOR OYSTER CREEK Recommended By NRC BWOG GPUN Parmaeter Description Y/N Cat Y/N Cat' Y/N Cat -Justification D-26 Turbine Bypass Valve- - -

Y 3- Y 3 BWROG Issue 11.

Position D-27 Condensate Hotwell Level - -

Y 3 Y 3 BWROG Issue 11.

D-28 Condenser Vacuum - -

Y 3 Y 3 BWROG Issue'11.

D-29 Reactor Recirculation - -

Y 3 Y 3 BWROG Issue 11.

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PROPOSED PARAE TER SET FOR OYSTER CREEK it: t Recannended By IftC BWOG N Parameter Description Y/N Cat Y/N Cat Justification Y/N Cat D-31 Drywell Isolation - - - -

Y 2 Needed to assure proper performance of the Valve Position containment system's function of isolating the reactor building and environs from the drywell under LOCA conditions.

D-32 58GTS Fan and Valve - - - -

Y 2 Key parameters needed to verify proper system Indication operation. Provides hold up of noble gases and removal of iodines and particulates prior to release through the stack.

D-33 Torus Pressure - -

Y 2 See A-7.

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TABLE I .

PROPOSED PARAMETER SET FOR OYSTER CREEK Recommended By NRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification Y 3 Direct indication of the ability to use plants D-34 MSIV Position - - - - -

main heat sink. It is also an entry condition to E0Ps and automatic scram signal.

D-35 Main Steam Flow - - - - Y 3 Indication of heat load on main heat sink. It would verify that steam is going to condenser vice torus or through a pipe break and is also an automatic MSIV isolation signal.

D-36 Core Spray Isolation - - - - Y 3 Needed to qualify core spray flow as flow to Valve Position the reactor -vs. through the test line, relief valve or line break.

D-37 CRD Flow - - - Y 3 CRD flow and pressure are required to assess the operability of this system to provide high pressure coolant make up and scram accumulator supply.

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TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Reconenended By .

NRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification D-38 CR0 Pressure - - - -

Y 3 CRD flow and pressure are required to assess (Accumulator Charging) the operability of this system to provide high pressure coolant make up and scram accumulator supply.

D-39 ESW Temp. Out of - - - -

Y 2 ESW outlet temperature and baffle plate dp are Heat Exchanger needed in conjunction with D-19 and D-20 to assure proper operation of the containment spray system.

D-40 ESW Baffle Plate dp - - - -

Y 2 ESW outlet temperature and baffle plate dp are

. needed in conjunction with D-19 and 0-20.to assure proper operation of the containment spray system.

D-41 Torus to DW and Rx - - - -

Y 3 Vacuum breaker position is extremely important Building to Torus to ensuring the torus will perform its steam Vacuum Breaker Position suppression function. Any open vacuum breaker is alarmed in the control with open/ shut indication available in the reactor building.

This is acceptable as is.

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m TABLE I PROPOSED PARAiETER SET FOR OYSTER CREEK Recormaended By NRC BWROG GPUN Parameter Description Y/N Cat Y/N Cat Y/N Cat Justification E-1 Drywell Area Radiation Y 1 Y 1 Y l High Range Reactor Building Area Y 2 N -

N - See BWROG Issue 12 and E-3.

E-2

- Y 2 Y 3 Y 3 Radiation studies indicate E-3 Reactor and Turbine See BWROG 1ssue 13,4-10 5 R/H in the Building Area Radiation radiation levels 10 Reactor Building one hour after a DBA LOCA.

Stack Noble Gas Y 2 Y 2 Y' 2 E-4 Concentration and Flow Rate 3 Y 3 Y 3 E-5 Stack and Turbine Y Building Particulate and Halogen Cor. centration

- - Deleted by NRC Errata, July, 1981 E-6 Radiation Exposure Meters - - - -

Airborn Radiohalogens Y 3 Y 3 Y 3 E-7 and Particulate 3 Y 3 Y 3 E-8 Plant Environs Addition Y 7 5' d it f ."

id ~ $

R, 8

TABLE I PROPOSED PARAMETER SET FOR OYSTER CREEK Recommended By NRC BWROG GPUN Parameter Description Y/H Cat Y/N Cat Y/N Cat Justification E-9 Plant and Environs Y 3 Y 3 Y 3 Radiation E-10 Wind Direction Y 3 Y 3 Y 3 E-ll Wind Speed Y 3 Y 3 Y 3 E-12 Estimatation of Y 3 Y 3 Y 3 Atmospheric Stability E-13 Reactor Coolant and Y 3 Y 3 Y 3 Delete sump sample, see BWROG Issue 14.

Drywell Suup Sample Use torus sample instead.

E-14 Drywell Hydrogen Y 3 Y 3 Y 3 and Gacma Spectrum

.? E Gl

<=

(D

R, 8

5 TABLE 11 STATUS OF MINIMUM PARAMETER SET F(It OYSTER CREEK LWTin % WIAL SEI5MIC yuni.ITY 0.0. Nts. GUIIM. .u CR Txftw ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATISI VARIABLES QUALIFICATION QUALIFICATION (See Note 1 Not Qualified See Note 3 See Note 1 Comply 0-1600psig N/A See Note 9 Yes A-1 RPV Pressure (Category 1)

See Note 3 See Note 1 Coagly -144" TAF N/A See Note 9 Yes A-2 RPV Water Level Not Qualified (Category 1) (See Note 4) +180 TAF A-3 Torus Water Teaperature Not Qualified See Note 3 See Note 1 See Note 5 0-5000F N/A See Note 9 Yes (Category 1)

Comply comply 12*-212" N/A Comply Yes A-4 Torus Water Level Comply Comply Inches (Category 1) -

Comply Comply 0-260 psia N/A Comply Yes A-5 Drywell Pressure Comply Comply (Category 1) 2 5' d

% .< . =

V$

R 8

I

9 TAKE 11 STATUS OF NINIDRIN PARAKTER SET FOR OYSTER CREEK U.C. uth, buwt a CR I x n ur tuvi--J I AL SEI5mt MITT DISPLAY LOCATION ASSURANCE REDUNDANCY RANGE RANGE SUPf*LY VARIAKES QUALIFICATION QUALIFICATION (See Note See Note 6 0-4000F N/A See Note 9 Yes A-6 gryme11 Temperature Not Quellfled See Note 3 See Note 1 (Category 1)

Do not cogly .5-+1.5 N/A Yes Not Qualified See Note 3 See Note 1 A-7 Torus Pressure P5I9 (Category 1) 0-301(H2 ) N/4 Comply Yes A-8 Bryvell Combustible Comply Comply CONIY Co"PT y 0-10%(02 )

Gas Concentration (Mr. 02 I (Category 1)

? 5' Y bl ~ $

a 8

m i

TABLE II STATUS OF MININUM PARAfETER SET FOR OYSTER CREEK U.C. Kth GUInt u cu Ts.ir w tuvan umL SEIMtIL v m ITT ASSURANCE REDUNDANCY RANCE RANGE SUPPt.Y DISPLAY LOCATION VARIABLES QUALIFICATION QUALIFICATION (See Note 1 See Note 3 See Note 1 Comply Comply 10-6-100 See Note 9 Yes 3-1 Neutron Fles (later) Percent Power (Category 1)

N/A N/A N/A N/A Comply Full in or N/A Yes 3-2 Centrol Red Position - not full in (Category 3)

N/A N/A Comply 0-1000 ppm N/A N/A 3-3 RCS Selvable Boron N/A N/A Concentration (Sample)

(Category 3)

- - - - - - - - - - See A - - - - - - - - - - - - - - - - - - Comply Core support 3-4 RPV Water Level plate to center (Category 1) line of MSL

?NY

% .* ?

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P, 8

e TABLE II STATUS OF MINIMUM PARAMETER SET FOR OYSTER CREEK REG. GUIDE FUu[R CR T30/ tty ERYlRunru.NI AL 5EI5MIC QUALITY 0.0.

ASSURANCE REDUNDANCY RANGE RANGE StFPLY DISPLAT LOCATINI VARIABLES QUALIFICATION QUALIFICATION (See Note 1

- - - - - - - Comply 15psta- See A-1 See A-1 3-6 RPV Pressure - - - - - - - - - - See A - - - -

1500psig (Cagegory 1)

- - - - - - - - - - See A - - - - - - - - - - - - - - - - - - C ompl y 0 to Design See A-5 See A-5 B-7 Drywell Pressure Pressure (Category 1)

N/A N/A N/A Do not Bottom to N/A No 8-8 Drywell Sump Level N/A comply top (Category 3)

- - - - - - - - - - See A-5. - - - - - - - - - - - - - - - - - - Comply 10psta- See A-5 See A-5 B-9 Drywell Pressure Design (Category 1) Pressure See Note 2 See Note 3 See Note 1 Comply Comply Closed - See Note 10 Yes B-10 Primary Containment Not Closed Isolation Yalve Position (Excluding Check Valves)

(Category 1)

INY

' % .* ?

t~5 P,,

8 I

e TABLE 11 STATUS OF MINIMUM PARAETER SET FOR OYSTER EREEK U.C. REG. GUIDt. FUutR FR Ixin w LNTAR m MIAL 5LI5F11C QUALIIT ASSURANCE REDUNDANCY RAMGE RANCE SUPPLY DISPLAY LOCATION VARIABLES QUALIFICATION QUALIFICATION

( ke Rote 11 3-11 Drywell Temperature - - - - - - - - - - See A - - - - - - - - - - - - - - - - - - - - - - - - N/A ------ See A A ------

(Category 1)

N/A Yes 5-12 Torus Pressure - - - - - - - - - - See A - - - -

(Category 1)

- - - - - - - - - - See A - - - - - - - - - - - - - - - - - - - - - - - - N/A See A-3 See A-3 3-13 Torus Water Temperature

- - - - - - - - - - See A - - - - - - - - - - - - - - - - - - - - - - - - N/A See A-4 See A-4 8-14 Torus Water Level (Category 1) o no H Ca @ O 00 <

q. @ . P.0

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N b b F O a a O I i i T r r S CA a a U IC v v T

A NI 5F s s T II i i S EL h h SA t A t u /

Q r h r o o f f t t s s a a Lm l l A0 T1 ev ev hT aA a a wC h h s I uF t t mI c c iL a a WAt A Np e / o E( D h D l p e

v d

e e g c L a ne t er r d ru e) t2 l) l3 et) f a1 e u er Isy Sy Aey r r pr l o ro l mo l g eg l eg S ee t e eTe s

E ut ct n t L ya aa yga e rC eC rec A B( R( DL(

I A 5 6 7 a

y 1 1 1 B S B lj ;llll lll : L_

n.

t TABLE II STATUS (F MINilGNt PARAKTER SET FIR OYSTER CREEK tzys.__.__wimL 5EI5ffl0 gunLITT U.C. Rh. halut .u CW TV.itur llUALIFICAT10ll QUAI.lFICATI0li A55tmANCE REDUNDANCY RANGE RANGE SIFPLY DISPLAY LOCATIS VARIAKE5 (See Note 11 C-2 Analysts of Primary N/A N/A N/A N/A Cosy 1y N/A N/A Coolant (Sample)

(Gamme Spectrum)

(Category 3)

See A - - - - - - - - - - - - - - - - - - C omp l y See A-1 See A-1 C-4 BPV Pressure ---------

(Category 1)

C-5 grymell Area Radiation Inst. does not exist for this variable N/A No (CCtegory 3) IRfhr 10 R/

1

%??

$~5 P.,

8 L

e TABLE 11 STATtFS OF plNIf9pt PMAfETER SET FM OTSTER CREEK D.C . prth. EWIUL .u CW Tunw tuva- - nist SEI5MIC QUnLITT DISPLAY LOCAY15 REDUNDANCY RANGE RANGE SUPPLY QUALIFICATION A551RANCE VMIAKES QUALIFICATION (See note 11 N/A N/A Do not Botten to WA Alare is C-6 3ryme11 Brain Samps WA WA 1op prowided comply Level in Radueste (Category 3) CR (Identifled and Weidentifled Leakage)

Pottom of See A-1 See A-1 C-7 Terms Mater Level - - - - - - - - - - See A - - - - -------------- ECCS sectfen (Category 1) 11ae to 5 ft above norms 1' ,

water level

~ 0-design See A-5 See A-5 _

C-8 Drywell Pressure - - - - - - - - - - See A - - - - -------------- - pressure (Category 1) (psig)

<-------- 15psla-1500 See.A-1 See A-1

- - - - - - - - - See A - - - - -----

C-9 Rtf arcssure psis (Category 1) 10psta-3 See A-5 See A-5 C-O Drywell Pressere - - - - - - - - - - See A - - - - -------------- ttaes design (Category 1) press. for concrete; 4 times design press, for steel l

% .* s*

S " $$

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8

7 a

TABLE II STATUS OF MINIfGBt PARAfETER SET F(Rt OTSTER CREEK tuva- wint SEI5 MIL MITT U.L. uth. Gulpt. -u LW sw.fter VARIAK ES QUALIFICATION QUALIFICATION ASSURANCE REDUNDANCY RANCE RANGE StFPLY DISPLAY LOCAT1ful (See Note 11' C-11 Dryuell N Comply Comply Cou91 7 Co'91 7 Co'91y 0-301 Comply Yes Concentrakten (Capability (Category 1) of operating from 12 psia

, to design press.)

C-12 grjasell Oxygen Comply Comply Comply Comply Comply 0-101 Couply Yes Concentration (Capaht11ty (Category 1) of Operating fross 17 psia to design pressure)

C-13 Containment Effluent N/A N/A N/A N/A Comply 10-6mcf/cc- N/A No Radioactivity-Itoble (See Note 7)10-?mct/cc Gases (Category 3)

C-15 Effluent Radioactivity See flote 2 N/A See Note 1 N/A Comply 10-6mc/cc- N/A No lloble Gases (See Note 7) 103mel/cc (Category 2)

EEd

% ? ."

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R, 8

1

i TABLE II STATUS OF MINIMUM PARAETER SET FOR OTSTEE CREEK U.0. KEG. GUIUt. ruar.u ER T30fr ur LRTIRunrsLRTAL SEI5MIC QUALITT ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATInN VARIABLES QUALIFICATION QUALIFICATION (See Note 1

- - - - - - - - - - See A - - - - ------------------- N/A See A-6 59e A-6 C-16 Drywell Teaperature (Category 1)

- - - - - - - - - - See A - - - - ------------------- N/A See A-7 See A-7 C-17 Torus Pressure (Category 1) ,

~

- - - - - - - - - - See A - - - - ------------------- N/A See A-3 See A-3 C-18 Torus Temperature (Category 1)

See Note 3 See Note 1 N/A Open/Close N/A See Note 10 Yes-C-19 Drywell Isolation Yalve Comply and Reactor Bldg.

Ventilation Valve Position ,"

(Category 2) -

a

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e- - _q l

TABLE 11 STATUS OF MINIMUM PARAK1ER SET FOR OYSTER CREEK 0.C. REG. GUIUt. FUutM CR IM.itur LNTIRUltiLMI AL SEISMIC QUALITY SUPPLY DISPLAY LOCATION ASSURANCE REDUNDANCY RANGE- RANGE VARIABLES QUALIFICATION QUALIFICATION (See Note 11 N/A N/A Comply 0-1101 design N/A Yes D-1 Main Feedwater Flow N/A N/A flow (Category 3)

N/A N/A 0-50 ft. Bottom to top N/A Yes D-2 Condensate Storage N/A N/A Tank Level (Category 3)

- - - - - - - - - - - - - - - - - Comply 12psfa-3psig See A-5 See A-5 D-4 Drywell Pressure - - - - - - - - - - See A 0-1101 design (Category 2) pressure

- - - - - - - - - - See A - - - - - - - - - - - - - - - - - - +12"-+212" Top of vent See A-4 See A-4 D-5 Torus idater Level to top of (Category 2) weir wall

%??,

E~$'

E 8

i

i TABLE 11

STATUS OF MININUM PARAMETER SET FOR OYSTER CREEK.

CR ist/ter 0.0 . Rtu. GUIUt routu SEI5MIC QUALITY DISPLAY LOCATION Enilnumw.niAL REDUNDANCY RANGE RANGE SUPPLT QUALIFICATION QUALIFICATION ASSURANCE (See note 11)

VARIA8LES Comply. 300F- See A-3 See A-3 D-6 Torus Water Teaperature - - - - - - - - - - See A - - - - - - - - - - - N/A 2300F (Category 2) See A-6 0-4000F 400F- See A-6

- - - - - - - - - - See A - - - - - - - - - - N/A D-7 Drywell Atmosphere

Do not 4400F Tesgerature comply (Category 2) Yes N/A Open Closed-not N/A See Note 3 See Note 1 closed, or 0 D-10 Safety Valve and Not Qualified Earv. Position-Flow to 50psig or Pressure in Discharge Line (Category 2)

?$Y

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I

&~$

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i

i TABLE 11 STATUS OF MINIMUM PARAMETER SET FOR OYSTER CREEK 0.C. REG. GUIDE FUutR CR T5Citw LRTInunntnIAL SEISMIC QUALITT ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATION VARIABLES QUALIFICATION QUALIFICATION (See Note 11 See Note 3 See Note 1 N/A Do not Top to See Note 9 Tes D-11 Isolation Condenser Not Qualified comply bottom Systen Shell-Side Water (Category 2)

See Note 3 See Note I N/A Comply Open or See Note 10 Yes D-12 Isolation Condenser Comply Closed System Valve Position See Note 2 (Category 2)

N/A See 0-1101 See Note 9 Yes D-15 Core Spray System Not Qualified See Note 3 See Note 1 Note 8 design flow Flow .

(Category 2)

%??

&~$

e

i TABLE II STATUS OF HINIMUM PARAMETER SET FOR OYSTER CREEK RLb. GUIDE FUNER CR IV.tr ar QUALITY 0.C.

EnvInunnr.n1AL SEI5MIC RANCE RANGE SUPPLY DISPLAY LOCATION ASSURANCE REDUNDANCY (See Note 11 QUALIFICATION QUALIFICATION VARIABLES 0-110% N/A Flow /No N/A N/A Does not N/A N/A comply, design flow Flow 0-17 SLCS Flow Indication (Category 3) Only flow No flow Ind.

Comply Bottom to M/A Yes N/A N/A N/A D-18 SLCS Storage Tank N/A top Level (Category 3) Yes Comply 0-1101 Comply See Note 3 See Note 1 N/A D-19 Containment Spray Not Qualified design fiow Flow (Category 2) Comply Yes See Note i N/A 0-400T 32-350T Not Qualified See Note 3 D-20 Containment Spray Heat Exchanger Outlet Temp.

(Torus Water Side)

(Category 2) 4

% .* Y V$

R 0

'I

TABLE II STATUS OF MINIMUM PARAMETER SET FOR OYSTER CREEK LRYlMUfwit.RI AL SEI5MIC QUALITT U.0. REG. GUIDE FUu[R CR T3E tv or .

VARIABLES QUALIFICATION QUALIFICATION ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATION (See Note D-21 Emergency Service Water Inst. does not exist for this variable. 320F- N/A No Teaperature to 2000F Containment Spray Heat Exchangers (Category 2)

D-22 Emergency Service Inst. does not exist for this variable. 0-1001 N/A No Water Flow to design flow Containment Spray Heat Exchangers (Category 2)

D-23 High Radioactivity N/A N/A N/A N/A Comply Top to N/A No Liquid Tank Level bottom indication (Category 3) in Radweste CR D-24 Emergency Ventilation See C-19 See C-19 See C-19 See C-19 See C-19 Open/ N/A Yes Damper Positon Closed (Category 2)

D-25 Status of Standby Power See Note 2 See Note 3 See Note 1 N/A Comply Voltages N/A Yes and Other Energy Currents Sources Important to Pressures Safety (Hydraulic Pneumatic)

(Category 2)

' ?$Y

% .< w l $~

. P,,

8 i

l

TABLE II STATUS OF MINIMUM PARAMETER SET FOR OYSTER CREEK ENVIRONMENTAL SEISMIC @ ALIT Y 0.C. REG. GulDE POWER CR TSC/ EOF VARIABLE 5' QUALIFICATION @ALIFICATION ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATION (See hote 11)

D-26 Turbine Bypass Valve N/A N/A N/A N/A Open/Close N/A N/A Yes Position (Category 3) **

D-27 Condenser Hotwell N/A N/A N/A N/A 0-60" N/A N/A Yes Level (Category 3)

D-28 Condenser Vacuum N/A N/A N/A N/A 0-30"Hg N/A N/A Yes (Category 3)

D-29 Reactor Recirculation N/A N/A N/A N/A 0-40,000 N/A N/A Yes Flow gpa (Category 3) 18 .< ."

S~$

R,

. 8

4 TABLE 11 STATUS OF MINIMUM PARAMETER SET FOR OYSTER CREEK ENVIRONMENTAL SE!SMIC @ALITY 0.C. REG. GulDE POWER CR' TSC/ EOF VARIABLES @ALIFICATION @ALIFICATION ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATION (See Note 11)

D-30 Shutdown Cooling Heat N/A NfA N/A N/A 0-4000F N/A N/A No Exchanger Outlet Temp. ..

(Category 3)

D-31 Drywell isolation - - - - - - - - - - See 2 - - - - - - - - - - - N/A Open/Close N/A See B-10. See B-10 Valve Position (Category 2)

D-32 SBGTS Fan and Valve (Later) See Note 3 See Note 1 N/A On/Off N/A Yes Indication (Fans)

(Category 2) Open/ Closed (Valves)

$5Y

% .< P V$

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8

= _ _ _ - _ _ _ - _ _ _ _

. i 1'

l TABLE 11 STATUS OF MINIMUM PARAMETER SET FOR OYSTER CREEK ENVIRONMENTAL SEI5MIC QUALITY 0.0. REG. GUIDE POWER CR ISC/ EOF VARIABLES -QUALIFICATION QUALIFICATION ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATION (See Note II)

D-33 Torus Pressure - - - - - - - - - - See A - - - - -------------------- See A-7 See A-7 (Category 2) ,,

D-34 MSIV Position N/A N/A N/A N/A Comply N/A .Yes (Category 3)

D-35 Main Steam Flow N/A N/A N/A N/A 0-4x106 N/A N/A Yes (Category 3) lbe/hr D-36 Core Spray Isolation N/A N/A N/A N/A Open/Close N/A N/A Yes Valve Position (Category 3)

?$Y

%??

$~$

P,, .

8

TABLE 11 STATUS OF MINIMUM PARAMtTER SET FOR OYSTER LREEK

. ENVIRONMENTAL SEISMIC QUALITV 0.0. REG. GUIDC POWER CR . ISC/ EOF VARIABLES QUALIFICATION QUALIFICATION ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATION (See hote 11)

D-37 CPD Flow 0-100gpm N/A N/A Yes (Category 3) ,

D-38 CRD Pressure N/A N/A N/A N/A 0-2000psig N/A N/A Yes (Accumulator Charging)

(Category 3) 0-39 ESW Temp. Out of N/A N/A N/A N/A N/A N/A No Heat Exchanger (Category 2) -

D-40 ESW Baffle Plate dp N/A No (Category 2)

D-41 Torus to DW and Rx N/A N/A N/A N/A Alarm N/A N/A Yes Bldg. to Torus Vacuum -

Breaker Position (Alarm)

(Category 3)

$$Y i; .< ?

$~5 P,,

2!

i TABLE Il STATUS OF MININUM PARANETER SET FOR OYSTER CREEK U.C . Rth. GUIDE FUut R CR Ixpr.w LNYInuwir.RI AL SE15PIl0 QUALITT QUALIFICATION ASSURANCE REDUNDANCY RANGE RANGE SUPrl.Y DISPLAY LOCATION VARIABLES QUALIFICATION (See Note {

E-1 Drywell Area Radiation Inst does not exist for this variable. IR/hr-107 No Nigh Range R/hr (Category 1)

N/A N/A N/A N/A Does not 10-IR/hr N/A Yes E-? neactor and Turbine comply to 104R/hr Building Area Radiation (Category 3)

E-4 Stack Noble Gas See Note 2 N/A See Note 1 N/A Comply 10-6u ct/cc- N/A No 105 uct/cc-0-110% vent Concentration and design flow Flow Rate (Category 2)

N/A N/A N/A N/A 10-II 10-3uct/cc- N/A No E-5 Stack and Turbine 102 uct/cc Building Particulate ucl{cc-10- 0-110% vent and Natogen Concentration (Category 3) uci/cc design flow O

y .< ?

$~$

P,,

/

8

i TABLE II STATUS OF MINIMUM PARAIETER SET FOR OYSTER CREEK _

twvInunrnNTAL SEI5MIC QUALITT U.C. REG. GUIDE- r-R CR IM.f ter ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATION VARIAN.ES' QUALIFICATION QUALIFICATION (See Note III 1 i

E-7 Airborne Radio- N/A N/A N/A N/A Comply 10-9uct/cc- N/A No halogens and Particulates 10-3ect/cc Portable Sampling (Category 3)

N/A N/A N/A Comply 10-3R/hr- N/A N/A E-8 Plant and Environs N/A 108 R/hr Radiation (Portable ons Instrumentation) PhojR/hr 10-(Category 3) 107 R/hr BETA radiation and low energy Photons.

N/A N/A N/A N/A Comply tiult1-channel N/A N/A E-9 Plant and. Environs Gasmia-Ray Radiation (Portable Spectrometer Instrumentation)

(Category 3)

N/A N/A N/A Comply 0-3600 N/A Yes E-10 Wind Direction M/A (Category 3) t

?EY '

W~$

l R 8

e TABLE II STATUS OF MINIMUM PARAK TER SET FOR OYSTER CREEK inTIRuprutnI AL SEISMIC QUALITY 0.C. REG. GUIDE rma CR Ixitar VARIABLES QUALIFICATION QUALIFICATION ASSURANCE REDUNDANCY RANGE RANGE SUPPLY DISPLAY LOCATifMt (See note 11)

E-11 Wind Spped N/A N/A N/A N/A Comply 0-30mps N/A Yes-(Category 3) (67 aph)

E-12 Estimation of N/A N/A N/A N/A Comply -50C- N/A Yes Atmospheric Stability . 1000 (Category 3) Accuracy

per 50 meters E-13 Reactor Coolant N/A N/A N/A N/A Comply Grab Sample N/A N/A and Drywell Sump

Sample (Category 3)

E-14 Drywell H2 , 02 N/A N/A N/A N/A Comply Grab Sample N/A N/A and Gaeuna Spectrum (Category 3)

P,,

8

't

,IDR 528 Ranr. O Page 56 cf 70 NOTES FOR TABLE II

1) GPU Nuclear has a documented quality assurance plan which, as a minimum, satisfies the requirements of 10CFR50, Appendix B. 1 GPU Nuclear's quality assurance plan has been reviewed and approved by the NRC. ,

Any. instrumentation which has to be replaced because of technical l inadequacies (performance or environmental qualification) will be procurred per the requirements of GPU Nuclear's quality assurance plan, which may or may not include the quality assurance requirements specified in USNRC Regulatory Guide 1.97, Revision 2.

The instruments in compliance with technical and environmental qualification requirements but lacking quality assurance docunentation shall be considered in compliance with R.G. 1.97 quality assurance requirements. Lack of quality assurance documentation for existing instrumentation will not require any modification to be performed at Oyster Creek.

2) Equipment located in a itild Environment

- 10CFR50.49(3)(iii) - 11 tid environment equipment is not included in the scope.

- Comments on the proposed rule (3) scope - The comission has determined that no additional requirements are necessary for mild environment equipment.

Requalification of Electrical Equipment

- 10CFR50.49(K) - Not required to requalify equipment previously qualified to the 00R guidelines. OCNGS equipment was qualified to 00R guidelines; therefore, R.G. 1.89 qualification requirements are not applicable.

3) The equipment that satisfies the range and environmental qualification will be considered seismically qualified if it satisfies requirements specified for OCNGS at the time the equipment was procurred and installed. Where documentation for seismic qualification of existing equipment does not exist, the equipment will be considered qualified to the original design criteria as specified in the FDSAR.

s

- '1TR 528 Rev.lL l Page 57 of 70 '

(Notes for Table II) (Continued)

\

4) The reactor water level system consists of four independent systems to

' monitor the entire range of reactor level. Three systems have redundant indication in the control room and the fourth one is single channel system.

5) The torus water temperature is monitored at four different locations in the torus. Each channel is recorded in the control room. All four channels are recorded on the sane recorder.

6) The drywell atmosphere temperature is monitored at five different locations in the drywell. Each channel is recorded in the control room.

All five channels are recorded on the same recorder.

7) Ragems Range Acceptable to NRC. P. B. Fiedler letter to fir. D. G. Eisenhut dated 02-23-82. NRC letter to P. B. Fiedler from D. M. Crutchfield dated 03-31-82 50-219 LS05-82-003-111.

8) The range required for core spray system flow is in compliance with R.G.

1.97 requirements for system II and not in compliance for system I.

9) Both instrument channels powered by the same diesel generator with provisions to transfer to other diesel generator.

10) The indication for the valve positions is powered from the power feeds that power the control circuits for the respective valves.

11) Those.R.G. 1.97 parameters which are to be available to the TSC/ EOF are the same as the parameter selection for the Oyster Creek SPDS, which includes all Type "A" variables. These variables will be available to the TSC/ EOF via the Oyster Creek SPDS and/or plant computer.

l l

l

TABLE III ACTIONS REQUIRED TO SATISFY R.G. 1.97 REQUIREMENTS FOR OCNGS MINIMUM PARAMETER SET AREAS OF NON-COMPLIANCE SYSTEM CR VARIABLE CAT. CODES EQ REDN RANGE .DSPL REMARKS / SCHEDULE - REFUELING OUTAGE A-1 RPV Pressure 1 2,3,4 X Plan to upgrade /llR B-6, C-4,'C-9 A-2 RPV Water Level 1 2,3 X X Plan to upgrade /12R A-3 Torus Water 1 3,4 X Plan to upgrade.

Temperature Required per Nureg 0783/llR B-13, C-18, D-6 A-6 Drywell 1 2,3,4 X X Plan to upgrade. Do not have a Temperature system for bulk temperature /llR B-11, C-16, D-7 A-7 Torus Pressure 1 2,3,4 X X X Plan to upgrade /12R B-12, C-17, B-38

?Ed

<

V\

P,,

8

TABLE III ACTIONS REQUIRED TO SATISFY R.G. 1.97 REQUIREMENTS FOR OCNGS MINIMUM PARAMETER SET'-

AREAS OF NON-COMPLIANCE SYSTEM CR .

VARIABLE CAT. CODES EQ REDN RANGE DSPL REMARKS / SCHEDULE - REFUELING OUTAGE B-3 RCS Boron 3 1 Grab Sample Concentration B-8 Dyrwell Sump Level 3 3 X X' Do not' plan to upgrade - See Note-l d' 5' d a, .< =

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TABLE III ACTIONS RIQUIRED TO SATISFY R.G. 1.97 REQUIREMENTS FOR OCNGS MINIMUM PARAMETER SET-AE AS OF NON-COMPLIANCE SYSTEM CR VARIABLE CAT. CODES EQ 'REDN RANGE DSPL REMARKS / SCHEDULE - REFUELING OUTAGE' B-15 Drywell Water 2 2 X X X X Do not have inst. Plan to install /12R.

l Level B-17 Drywell' Reference 1 2 X X X X Do not have inst. Plan to install /llR Leg Temperature l

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-y TABLE III ACTIONS REQUIRED TO SATISFY R.G. 1.97 REQUIREMENTS FOR.0CNGS MINIMUM PARAMETER SET AREAS OF NON-COMPLI ANCE SYSTEM CR VARIABLE CAT. CODES EQ REON. RANGE DSPL REMARKS / SCHEDULE - REFUELING OUTAGE C-2 Analysis of 32 Grab Sample Reactor Coolant C-5. Drywell Area 1 3,16 X X -X X Inst. does not exist plan to install /11R-Radiation E-1 C-6 Drywell Sump 3 3- X X See Note 1 and B-8 and Equipment Drain Tank Level

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,x TABLE III ACTIONS REQUIRED TO SATISFY R.G. 1.97 REQUIREMENTS FOR OCNGS MINIMUM PARAMETER SET AEAS OF NON-COMPLI' NCE SYSTEM T VARIABLE CAT. CODES EQ REDN RANGE DSPL REMARKS / SCHEDULE - REFUELING OUTAGE D-10 Safety Valve and 2 3,6 X Do not plan to upgrade - See Note 2 Emrv. Position Indication D-11 Isolation 2 7 X X Plan to upgrade for EQ only Condenser Shell- - See Note 3/llR Side Water Level D-15 Core Spray System 2 7 X X Plan to upgi - the system that Flow does not meet range requirements /llR D-17 SLCS Flow 3 1 X Do not plan to upgrade - See Issue 9 of BWROG 2 5' d g ,< = -

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Y TABLE III ACTIONS REQUIRED TO SATISFY R.G.1.97 REQUIREMENTS FOR OCNGS MINIMUM PARAMETER SET-AREAS OF NON-COMPLIANCE SYSTEM CR VARIABLE CAT. CODES EQ REDN RANGE DSPL REMARKS / SCHEDULE - REFUELING OUTAGE-D-19 Containment Spray 2 7 X Plan to upgrade /11R Flow D-20 Containment Spray 2 7 X Plan to upgrade /11R Heat Exchanger Outlet. Temp.

(Torus Water Side)

D-21 Emergency Service 2 7,9 X Plan to use intake canal temp. for-Water to Containment this application Spray Heat Exchanger Temperature 0-22 Emergency Service 2 7,9 .X X X Inst. does not exist - plan to install /12R Water Flow to Containment Spray Heat Exchangers D-23 High Radioactivity 3 10 X Do not plan to upgrade - See Note 4 Tank Level D-25 Status of Standby 2 12 X Only inst. air pressure transmitter Power and Other needs upgrading /llR Energy Sources Important to Safety

= < = -

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' TABLE III ACTIONS. REQUIRED T0 SATISFY.R.G. 1.97 REQUIREMENTS FOR OCNGS MINIMUM PARAMETER SET.

AREAS OF NON-COMPLIANCE SYSTEM CR

. VARIABLE- CAT. CODES EQ REDN RANGE DSPL REMARKS / SCHEDULE - REFUELING OUTAGE-D-39 ESW Temp. out of 2 4,7 X Plan to install /12R Heat Exchanger

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TABLE III ACTIONS REQUIRED TO SATISFY R.G. 1.97 REQUIREMENTS FOR 0CNGS MINIMUM PARAMETER SET.

AREAS OF NON-COMPLIANCE SYSTEM CR VARIABLE CAT. CODES EQ REDN RANGE DSPL REMARKS / SCHEDULE - REFUELING OUTAGE-D-40 ESW Baffle Plate 2 4,7 X Plan to install /12R dp

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TABLE III ACTIONS REQUIRED TO SATISFY R.G. 1.97 REQUIREMENTS FOR-0CNGS MINIMUM PARAMETER SET AREAS OF NON-COMPLIANCE SYSTEM CR VARIABLE CAT. CODES EQ REON' RANGE DSPL REMARKS / SCHEDULE - 7. FUELING OUTAGE E-3 Reactor and 3 17 X Plan to upgrade - will require upgrading-Turbine Bldg. some ARMS.to meet required range Area Radiation (See Note 6) /-to be determined E-4 Stack Noble Gas 2 18 X See Note 5 Concentration and Flow Rate E-5 Stack and Turbine 3 18 X See Note 5 Bldg. Particulate and Halogen Concentration

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TABLE III

' ACTIONS REQUIRED TO SATISFY R.G. 1.97 REQUIREMENTS FOR OCNGS MINIMUM PARAMETER SET AREAS OF NON-COMPLIANCE SYSTEM CR VARIABLE CAT. CODES EQ REDN RANGE DSPL REMARKS / SCHEDULE - REFUELING OUTAGE E-7 Airborne Radio- 3 19 Portable halogens and Particulate E-8 Plant Environs 3 19 Portable Inst.

Radiation E-9 Plant and Environs 3 19 Portable Radiation

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TABLE'III m ACTIONS REQUIRED TO SATISFY R.G. :1.97 REQUIREMENTS FOR OCNGS MINIMUM PARAMETER SET-

~ .

AREAS OF NON-COMPLIANCE -

SYSTEM CR

. VARIABLE CAT. CODES EQ-REDN RANGE DSPL. REMARKS / SCHEDULE - REFUELING OUTAGE E-13 ' Reactor Coolant 3 21 Sample See Issue 14 of BWROG to take and Drywell Sump Torus instead of Drywell Sump Sample E-14 .Drywell. Hydrogen 3 21 Sample Oxygen and Gamma Spectrum

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r Plage 69 of 70 NOTES FOR TABLE III 1)

There is no indication of actual level in either the Drywell Sump.or Drywell Equipment Drain Tank. Hi level alarms are annunciated in the New Radwaste Control Room along with flow integrators. They Drywell Sucp fill rate is indicated and. alarmed in the Main Control Room (i.e.

unidentified leakage) and pump run time integrator indication <is available in the 480V room in the Turbine Building. These indications are adequate for determination of leak rate. .,

2) An adequate environmentally qualified acoustic systen is not available at this time. ~

3) ' Actual level indication is 0-10 feet vice R.G.1.97 span of 0-12 feet..^

Since maximum allowed operating level is 7.7 feet by procedure 307, 10 feet is an adequate upper limit. -s

4) Information is displayed in Radwaste Control Room may use phone or radio to transfer this information to Main Control Room

5) Information is in computer location adjacent to Control Room.

6) GPU Nuclear is currently performing a study (TDR 498) which will address inadequacies of the Ant 15 at Oyster Creek.

N s

y 'IDR 528 Pav.- 1 Page 70 of 70 SYSTEtt CODES

1. Reactivity Control

2. Core Cooling

3. Reactor Coolant System Integrity a

I* 4. Containment Integrity '