ML20213E625

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Forwards Rationale & Revs to Proposed Changes to STS to Reflect Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant & Environs Conditions During & Following Accident, Contained in Reg Guide 1.97,Rev 2
ML20213E625
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 10/12/1983
From: Mattson R
Office of Nuclear Reactor Regulation
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML20213E629 List:
References
RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8310180568
Download: ML20213E625 (18)
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Text

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MEMORANDUM FOR: Darrell G. Eisenhut, Director Division of Licensing ggg FROM: Roger J. Mattson, Director ,

Division of Systems Integration "

SUSJECT: TECHi!! CAL SPECIFICATI0 tis FOR POST ACCIDEt:T

. M0filTORING It!STRUlIENTATI0ft In accordance with NRR Office Letter No. 38 the Instrumentation and Control Systems Branch (ICSR) is proposing a change to the Standard Technical Specift-cations (STS). The change will update the STS to reflect the recomendations contained in Regulatory Guide 1.97 Revision 2, "Instrsmentation For Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environs Conditions During and Following an Accident". As Enclosure I we are providing the supporting rationale for this change. As Enclosure 2 we are providing revised STS pages.

I It is our recomendation that the revised STS he implemented imediately on OL reviews and be included in the next publication of Westinghouse, Combustion l Engineering, Babcock and Wilcox and General Electric STS.

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Roger J. Mattson, Director Division of Systems Integration DISTRIBUTION:

Enclosures:

Central File As stated ICSB R/F M. Virgilio (PF)(2) cc: C. Thomas J. Joyce C. Rossi

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ENCLOSURE 1 RATIONALE FOR PROPOSED STANDARD TECHNICAL SPECIFICATION CHANGE The Standard Technical Specifications (STS) currently impose limiting t

conditions for operation and surveillance requi,rements on the post-accident monitoring instruments and include examples of the instru-mentation that should be included in an applicant's technical specifica- .

tion submittal. Using the guidance contained in the bases section of the STS each applicant for an operating license develops a plant specific table to be included in the technical specification submittal listing the post-accident monitoring instrumentation. The bases section of the current STS references the December 1975 edition of Regulatory Guide 1.97 "Instrumenta-tion For Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions Durjng and Following an Accident" and NUREG-0578, "TMI-2 Lessons Learned Task Force Status Report and Short-Term Recommendations". The proposed change contained herein updates the STS to reflect the recently issued Regulatory Guide 1.97, Revision 2 and provides additional guidance as to which instruments should be included in the applicant's technical speci-fication submittal.

o On December 17, 1982 all licensees of operating reactors, applicants for operating licenses and holders of construction permits were sent a copy of Generic Letter No. 82-33 (Supplement I to NUREG-0737). This letter included guidance on post-accident monitoring instrumentation through an endorsement of Regulatory Guide 1.97, Revision 2. Regulatory Guide 1.97, Revision 2 divides the post-accident monitoring instruments into

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l three categories providing a graded approach to requirements depending on the importance to safety of the measurement of a specific variable. Cate-gory 1 includes the most stringent requirements and is intended for key variables. Category 2 includes less stringent requirements and generally e applies to instrumentation designated for indicating system operating status and instrumentation provided to furnish information regarding the .

release of radioactive materials. Category 3 is intended to provide re-quirements that will ensure high-quality, off-the-shelf instrumentation is obtained and applies to backup and diagnostic instrumentation. Al -

though the Regulatory Guide does not include explicit guidance on tech-nical specifications it does state that the Category 1 instrumentation "should be available prior to an accident except as provided in paragraph 4.11. " Exception", as defined in IEEE Standard 279 or as specified in the Technical Specifications" (C.1.3.1). For Category 2 instrumentation the Regulatory Guide states: "the out-of-service interval should be based on normal technical specification requirements on out-of-service for the sys-tem it serves where applicable or where specified by other requirements" (C.I.3.2).

Based on the guidance contained in Regulatory Guide 1.97, Revision 2 we recommend that the instrumentation provided to indicate system operating status, furnish information regarding the release of radioactive mater-ials and furnish diagnostic information (Category 2 and 3 as defined in Regulatory Guide 1.97 Rev. 2) be deleted from the post-accident monitor-ing instrumentation specification. We recommend that the illustrative table provided in the STS be revised to include only key variables (Category 1) consistent with the recommendations contained in Regulatory Guide 1.97, Revision 2. For those instruments of lesser importance

provided to indicate system operating status, furnish information regard-ing the release of radioactive materials and furnish diagnostic informa-tion we recommend a change to STS Section 6.8 " Procedures and Programs" to provide the appropriate limiting conditions for operation and surveil-lance requirements. Through a revision to STS'Section 6.8 programmatic requirements wi.11 provide periodic surveillance of the Category 2 and 3 instrumentation and appropriate actions for cases when Category 2 and 3 instruments are inoperable. These programmatic requirements include pre-planned operating procedures that address back-up instruments to be used in the event that Category 2 or 3 instruments are inoperable and admini-i strative controls for returning the inoperable instruments to operable status as soon as practicable. These requirements provide incentives to restore instruments to operable status without restricting plant operation.

In addition, we recommend revising the bases section of the STS to refer-ence Regulatory Guide 1.97, Revision 2 and to specify that the technical specifications on post-accident monitoring instrumentation address only key variables as defined in the Regulatory Guide. Although plant specific considerations will necessitate having different monitored parameters as key variables the appropriate guidance is provided for developing plant specific technical specifications in the revised bases section.

We believe that the proposed STS revision contained herein clarifies the staff's position with regard to technical specifications on instrumenta-tion to assess plant and environs conditions during and following an acci-dent and, therefore, reduces the uncertainty as to what the staff con-i siders acceptable in the area of post-accident monitoring. The impact on i

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industry should be positive in that the proposed STS revision narrows the scope of the instrumentation explicitly covered by limiting conditions for operation and surveillance requirements to those instruments that monitor key variables.

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o ENCLOSURE 2 w

TABLE 3.3 ACCIDENT MONITSRING INSTRUMENTATION REQUIRED MINIMUM NO. OF NO. OF INSTRUMENT (ILLUSTRATIONAL ONLY) CHANNELS CHANNELS Neutron Flux 2 1 Coolant Level in Reactor 2 1 BWR Core Thermocouples 4/ core quadrant 2/ core quadrant RCS Pressure 2 1 Drywell Pressure 2 1 Drywell Sump Level 2 1 Primary Containment Pressure 2 1 Primary Containment Isolation Valve Position 2/ Valve 1/ Valve Radioactivity Concentration in Circulating Primary Coolant 2 1.

Drywell Drain Sumps Level 2 1 Suppression Pool Water Level 2 1 Containment Hydrogen Concentration 2 1 Drywell Hydrogen Concentration 2 1 Containment Oxygen Concentration 2 1 Drywell Oxygen Concentration 2 1 ,,

Reactor Building Area Radiation 2 1 '.-

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j, TABLE 3.3 ACCIDENT MONITORING INSTRUMENTATION REQUIRED MINIMUM NO. OF NO. OF INSTRUMENT (ILLUSTRATIONAL ONLY) CHANNELS CHANNELS i

!#4ieutron Flux 2 1 f#ACS Hot leg Water Temperature C D 8 j' M 1 JES Cold Leg Water Temperature &

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/ 4 Coolant level In Reactor 2 1 j Containment Sump Water Level (Wide Range) 2 1

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i ontainment Pressure 4 (Stainment Isolation Valve Positions 2

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1/ Valve 4/ core quadrant 2/ core quadrant

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ps eE. / edioactivity Concentration In Circulating Primary Coolant 2 1 Containment Hydrogen Concentration 2 1 2MN 1

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Levelteam Generator Level (w A--)

/-* densate Storage Tank Water level 1 I

/ tainment Area Radiation (High Range) 2 1 l Auxiliary Feedwater Flow (BgPlants) 2 1 4

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BASES Accident Monitoring Instrumentation The OPERABILITY of the accident monitoring instrumentation ensures that

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sufficient information is available on selected- plant parameters to monitor and assess these variables following an accident'. The instrumentation in-cluded in this specification are those instruments provided to monitor key -

variables, designated as Category 1 instruments following the guidance for classification contained in Regulatory Guide 1.97 Revision 2, "Instrumenta-tion For Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident." l 4

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ALL STS -

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a 6.8 PROCEDURES AND PROGRAMS 6.8.4 The following programs shall be established, implemented and maintained:

A program which will ensure the capability to monitor plant variables and systems operating status during and following an accident. This program shall include those instruments -

provided to indicate system operating status and furnish information regarding the release of radioactive materials (Category 2 and 3 instrumentation as defined in Regulatory Guide 1.97 Revision 2) and provide the following:

(i) preventive maintenance and periodic surveillance of instrumentation.

, (ii) pre-planned operating procedures and back-up instru-mentation to be used if one or more monitoring instruments become inoperable.

(iii) administrative procedures for returning inoperable instruments to OPERABLE status as soon as practicable.

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