ML20010E595

Forwards FSAR Changes Re Radiological Noble Gas Effluent Monitors & Improved in-plant Iodine Instrumentation Under Accident,For Incorporation in Revision 7 to FSAR

ML20010E595
Person / Time
Site:	Wolf Creek, Callaway
Issue date:	08/31/1981
From:	Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SLNRC-81-080, SLNRC-81-80, NUDOCS 8109080018
Download: ML20010E595 (5)

Text

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SNUPPS Standardized Nuclear Unit Power Plant System 5 Choke Cherry Road Nicholas A. Petrick Rockville, Maryland 20050 Executive Director (301) 86M010 August 31, 1981 SLNRC 81-080 FILE: 0541 SUBJ: ETSB Review Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Docket Nos.: STN 50-482, STN 50-483, and STN 50-486

Dear Mr. Denton:

The attached FSAR changes will be incorporated in Revision 7 to the SNUPPS FSAR.

Very truly yours, fM\RC Nicholas A. Petrick RLS/dck/3a15

Enclosure:

FSAR pp. 18.2-54, 1C.3-4, and inserts gj" 9, j.

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18.2.12.2 SNUPPS Response Radiological Nob 3e Gas Effluent Monitors The SNUPPS design.provides a high range noble gas radiation monitor for each of the release paths listed below. Each monitor will include detectors covering a range shown below:

MONITOR RANGE Plant unit vent 107 to 10*S pCi/cc (GT-RE-21B)

Radwaste building effluent 107 to 10+5 pCi/cc (GH-RE-10B)

The locations of these monitors are given as the P& ids for their respective system. Separate monitoring capability for the condenser system air removal exhausts through system the plant vent. isPadiation not provided because monitoring cf thc main ctca linco cr ctcam cystcm cafety valvcc ic bcing this (IN ctudicd, but a cpecific design is not available.

Continuous indication will be pr.ovided in the control room for each monitor. Each monitor will be recorded in the control room.

The system / methods for monitoring and analysis will be incor-porated into Section 11.5 of the FSAR upon completion of the design. The readouts from the high range monitors will be input to the plant computers. This information will then be accessible from the technical support center and the emergency operations facility.

The procedures used to calibrate the instruments and calculate release rates will be incorporated into the procedures for the respective facilities. I Nstgy 3 4

Provisions for Continuous Sampling of Plant Effluents for Post-Accident Releases of Radioiodines and Particulates The SNUPPS design will provide continuous sampling for effluent radiciodines. The high range noble gas effluent monitors described above include the capability to obtain grab samples.

The sampling will be accomplished with absorption charcoal filters or other media. The sampling system criteria for all airborn'e monitoring systems are provided in Section 11.5.2.3.1.3 of the FSAR. After collection, laboratory analyzers will be used to quantify iodine releases. A backup power source will be provided for sample collection and analysis equipment to ensure operation for a minimum of 7 consecutive days. The procedures for each facility will discuss the methods and counting equipment used to determine releases. The expected doses from obtaining and counting a sample will be presented in a revision to the FSAR. < TNSERT C.

18.2-54 Rev. 5 7/81 .

INSERT A The SNUPPS design includes gamma detectors to monitor the plume from the main steam power-operated relief valves and to monitor the steam discharge from the turbine-driven auxiliary feedwater pump. Additional information on this monitoring system will be provided at least four months prior to fuel load of the first SNUPPS unit.

INSERT B The following additional information will be provided at least four months prior to fuel load of the first SNUPPS unit:

A. System description information including energy depen-dence or response, range and sensitivity with respect to Xe-133, vendor model number, and methods used to assure representative measurements and background cor-rection.

B. The calculational methods or procedures to be used for converting instrument readings to release rate per unit time based on exhaust air flow and considering radio-nuclide spectrum distribution as a function of time after shutdown.

INSERT C Additional information regarding how the SNUPPS design meets the recommendations of Table II.F.1-2 and the provisions for approx-imate isokinetic sampling will be trovided at least four months prior to fuel load of the first SNUPPS unit.

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SNUPPS In view of the fact that these systems are designed to preclude - y~

operation during an accident, upgrading the testing and sur- -

i veillance of these systems is not justified. --

/N'IN SE9tT D 18.3.4.3 Conclusion The SNUPFS design includes provisions to insure the integrity of fluids systems which are postulated to contain highly contaminated fluids following a design basis accident. The t provision will be based on the preservice and inservice tests required by the ASME Code. These provisions provide assurance that thes'e systems will perform their intended functions, including leaktightness, following a design basis accident.

This commitment satisfies Item III.D.l.1 of NUREG-0737.

18.3.5 IMPROVED IN-PLANT IODINE INSTRUMENTATION UNDER ACCIDENT CONDITIONS (II.D.3.3)

Refer to each Site Addendum.

18.3.6 CONTROL ROOM HABITABILITY (III.D.3.4) 18.3.6.1 NRC Guidance per NUREG-0737 Pos. tion In accordance with Task Action Plan Item III.D.3.4 and control '*

room habitability, licensees shall ensure that control room --

operators will be adequately protected against the effects of accidental release of toxic and radioactive gases and that the nuclear power plant can be safely operated or shut down under design basis accident conditions (Criterion 19, " Control Room,"

of Appendix A, " General Design Criteria for Nuclear Power Plants," to 10 CFR Part 50).

Clarification (1) All licensees must make a submittal to the NRC regardless of whether or not they met the criteria of the referenced Standard Beview Plans (SRP) sections. The new clarifica-tion specifies that licensees that meet the criteria of the SRPs should provide the basis for their conclusion that SRP 6.4 requirements are met. Licensees may estab-lish this basis by referencing past submittals to the NRC and/or providing new or additional information to sup-plement past submittals.

(2) All licensees with control rooms that meet the criteria of the following sections of the Standard Review Plan:

2.2.1-2.2.2 Identification of Potential Hazards in Site Vicinity, i 2.2.3 Evaluation of Potential Accidents, and "

i 6.4 Habitability Systems Rev. 5  !

18.3-4 7/81 ,

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- INSERT 0-The SNUPPS Utilities will have a program to reduce leakage from systems outside containment that would or could contain highly

- radioactive fluids in a post-accident situation. The programs J will meet Item 111.D.1.1 of NUREG-0737, modified as required for

- the SNUPPS design. Detailed information on_the program and necessary changes-from NUREG-0737 such as excluded systems and their: Justification for_ exclusion will be provided at least four months prior to fuel load of_each SNUPPS unit.

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