ML17258A762
| ML17258A762 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 01/30/1981 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8102060558 | |
| Download: ML17258A762 (13) | |
Text
REGULATORY FORM'AT'ION DISTRIBUTION 8 EM (BIDS)
ACCESSTON NBR; 8102060558 DOC ~ DATE! 81/01/30 NOTARIZED:
NO DOCKET' FACIL450 244 Robert Emmet Ginna Nuclear Plants Unit 1i Rochester G
05000244 AUTH',NAME AUTHOR AFFILIATION MAIERpJ ~ E, Rochester Gas Il Electric Corps RECIP ~ NAME RECIPIENT AFFILIATION CRUTCHFIELDiD~ M-Operating Reactors Branch 5
SUBJECT>: Forwards response to NUREG 0737 Item IJ",F,i re noble~ gas effluent-monitor per 80i230 ltr;New monitor to be installed by 820i01 will= meet TMI action: plan requirements; DISTRIBUTION CODE:
AORTAS COPIES RECE'IVES:lTR $ ENCl I,'IZE: I
'ITLE!
Response
to NURKG 0737 TMI Action Plan Regmts's NOTES!1 copy!SEP Sect; ~ Ldr'.
05000244 REC IPIENT'D CODE/NAME ACTION:
CRUTCHF IELD 05 INTERNAL! DEP DIRgDHFS 21 DIRECTOR q DL i 4 DIRKCTORqDST'7 OELD PDR 02".
COPIES LTTR ENCL 7
7 1
1 1
1 1
0 1
1 RECIPIENT ID CODE/NAME DIRECTORS'E 15 DIRECTORgDSI, 16 IE,Ei 12"'R 18 REG. FILE 01 COPIES'TTR ENCL 1
1 1
2 2
3 3
1 1
EXTERNAL! ACRS NSIC 22" 04 16 16 1-LPDR 03 1
1 S~
TOTAL NUMBER OF COPIES'EQUIRED:
LTTR 8
ENCL
4 I
p
'C, 0
I I m
N
,I H
lfiFSZS
'SZJl Z
ill iran'll
!SISfiN
= ROCHE'TER GA$>AND ELECTRIC CORPORATION o
89 EAST AMOHN E~%,MA IF.R
~~RICE PRRI DENT, i l>Crl
~-'L:,I,
<<~~
NIR '~
Laal OaIa&4 IT/11 j AVENUE, ROCHESTER, N.Y. 14649
~ '..
TELEPHONE AREA CODE 715 546.2700 l
1 CI" CD UJ Gx January 30, 1981 Director of Nuclear Reactor Regulation Attn:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch g5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Clarification of TMI Action Plan Requirements (NUREG 0737)
R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Crutchfield:
NUREG 0737 contained requirements for submittal by January 1,
1981 of documentation on several of the TMI Action Plan items.
Our letter dated December 30, 1980 committed to provide additional information concerning Item II.F.1, Attachment 1, Noble Gas Effluent Monitor, by February 1, 1981.
Preliminary information concerning noble gas effluent monitoring was submitted on December 15, 1980.
At that time we indicated that our intent was to upgrade an existing monitor on the condenser air ejector to extend its range.
We now plan instead to install a new monitor which is independently capable of meeting the NUREG 0737 requirements.
Attachment A to this letter is intended to demonstrate that, the systems to be installed by January 1,
1982 will comply with the NUREG 0737 requirements.
Even though a pre-implementation review of modifications performed for this item has not been indicated, we request that you review the information in the attachment and provide us with any comments you have at an early date to avoid any waste of effort and resources.
Very truly yours, JEM:ng Jo.n E. Maier Pc yI, 5
ATTACHMENT A Rochester Gas 8 Electric Corporation
Response
Xo NUREG 0737 Item II.F.l, Attachment 1
Noble Gas Effluent Monitor January 30, 1981
RG&E Response to NUREG 0737 Item II.F.1, Attachment. 1, Noble Gas Effluent Monitor NRC Position n
Noble gas effluent monitors shall be installed with an extended range designed to function during accident, conditions as well as during normal operating conditions.
Multiple monitors are considered necessary to cover the ranges of interest.
(1)
Noble gas effluent monitors with an upper range capacity of 10 p Ci/cc 5
(Xe-133) are considered to be practical and should be installed in all operating plants.
(2)
Noble gas effluent monitoring shall be provided for the total range of concentration extending from normal condition (as low as reasonably achievable (ALARA)) concentrations to a maximum of 10 p Ci/cc (Xe-133).
Multiple monitors are considered to be necessary to cover the ranges of interest.
The range capacity of individual monitors should overlap by a factor of ten.
Chan es to Previous Re uirements and Guidance This requirement was originally issued by letters to all operating power plants dated September 13 and October 30, 1979.
Significant changes in requirements or guidance are:
(1)
Deletion of specific range overlap requirement.
(2)
Specifies that offline monitoring is not required for safety valve and dump valve discharge lines.
(3)
Implementation date changed from January 1,
1981 to January 1,
1982.
(4)
Specifies that in)inc sensors are acceptable for concentrations between 10 p Ci/cc to 10 p Ci/cc of noble gases.
Clarification Licensees shall provide continuous monitoring of high-level, post-accident releases of radioactive noble gases from the plant.
Gaseous effluent monitors shall meet the requirements specified in the enclosed Table II.F.1-1.
Typical plant effluent 'pathways to be monitored are also given in the table.
1 (2)
The monitors shall be capable of functioning both during and following an accident.
System designs shall accommodate a design-basis release and then be capable of following decreasing concentrations of noble gases.
January 30, 1981
(3)
Offline monitors are not required for the PWR secondary side main steam safety valve and dump valve discharge lines.
'For this application, externally mounted monitors viewing the main steam line upstream of the valves are acceptable with procedures to correct for the low energy gammas the external monitors would not detect.
Isotopic identification is not required.
(4)
Instrumentation ranges shall overlap to cover the entire range of effluents from normal (ALARA) through accident conditions.
The design description shall include the following information.
(a)
System description, including:
(i) instrumentation to be used, including range or sensitivity, energy dependence or response, calibration frequency and technique, and vendor's model number, if applicable; (ii) monitoring locations (or points of sampling), including description of methods used to assure representative measurements and background correction; (iii) location of instrument readout(s) and method of recording, including description of the method or procedure for transmitting or disseminating the information or data; (iv) assurance of the capability to obtain readings at least every 15 minutes during and following an accident;
- and, (v) the source of power to be used.
(b)
Description of procedures or calculational methods to be used for converting instrument readings to release rates per unit time, based on exhaust air flow and considering radionuclide spectrum distribution as a function of time after shutdown.
A licabilit This requirement applies to all operating reactors and applicants for operating license.
Im lementation Implementation must be completed by January 1, 1982.
e of Review A post-implementation review will be performed.
January 30, 1981
Documentation Re uired Licensees and licensing applicants should have available for review the final design description of the as-built system, including piping and instrument diagrams together with either (1) a description of procedures for system operation and calibration, or (2) copies of procedures for system operation and calibration.
Operating Reactors--By, January 1,
1981 operating reactors should have available for review the final design details of the implementation of the above position and clarifications. If deviations to the above position or clarification are necessary, provide detailed explanation and justification for the deviations by January 1, 1981.
RG&E Res onse I.(a)
System Description
Plant Vent, Containment. Vent, and Condenser Air Ejector* Effluents (i)
Instrumentation to be Used:
An Eberline air sampling system has been purchased for installation by January 1,
1982.
The system consists of an air sampling unit for each vent, stack and central control consoles in the Control Room and TSC.
Ran e, Sensitivit Ener Res onse:
Approximately 10 to 10 p Ci/cc for Xe; 2 20% 40 Kev through 1.33 Mev.
Calibration Fre uenc and Techni ue:
The calibration frequency wall be xn accordance with Technical Specification 4.1 which requires calibration of the radiation monitoring system during each refueling. It is intended that calibration will be performed by correlating monitor response to known gas concentrations introduced in the sampler
- assembly, or to radiation sources simulating high gas concentrations.
Alternatively, on line monitor calibration can be performed by correlating actual sample analysis data with Sping-4 readings.
Vendor Model Number:
Eberline Sping-4 Samplers and Control Terms.nals (ii) Monitorin Locations:
Plant Vent and Containment Vent Az.r Samp ers - Intermediate Bldg. El. 298'4".
Plant Vent Sample Inlet - Intermediate Bldg. El. 310'.
Containment Vent Sample Inlet - Intermediate Bldg. El. 320'.
Air Ejector Sampler Turbine Bldg. El. 289'6".
Air Ejector Sample Inlet - Turbine Bldg. El. 292'7".
These sample locations monitor the final release points and include all discharge inputs.
Problems associated with moisture and high temperatures in air ejector exhaust are being investigated. January 30, 1981
L P
Re resentative Sam lin :
, Single probe isokinetic nozzles at vent centerla.ne have been designed in accordance with ANSI-N.13.1-1969.
Back round Correction:
Each airborne radioactivity channel wall automatically compensate'or variable background radioactivity.
(iii) Location of Instrument Re'adouts:
Control Consoles in Control Room and TSC.
Method of Recordin Microprocessor controlled printout.
Data Transmission:
3 shielded 516 AWG pairs from samplers to control consoles.
(iv) Assurance of Obtainin Readin 's at Least Ever 15 Minutes:
-Data, status, and channel number are printed every 10 minutes when status is high alarm or calibrate.
(v)
(b)
II.(a)
Power Source:
Instrument, Bus 1B (backed by emergency diesel generator).
In addition, each sampler has an internal 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery backup.
Calculational Procedures for Obtainin Release Rates The Eberline Control Consoles are located in a low radiation environment.
and can be programmed with the necessary constants and conversion factors for direct readout of release rates (p Ci/sec).
System Description
Main Steam.Safety Valves, Power Operated Relief Valves (PORVs) and Turbine Driven Auxiliary Feedwater Pump (TAFWP) Discharge Instrumentation to be Used:
This system requires instrumentatxon for monitoring releases from the main steam safety valves, PORVs and turbine driven auxiliary feedwater pump (TAFWP).
An Eberline dual steamline monitor consisting of two SA-11 sampling assemblies, two IB-4HTCC interfaces, one dual channel data aquisition module DAM-3, and two CLI-1 communication line isolators will be purchased for installation by 1/1/82.
The outputs of the steamline monitors and the open/close status of the release paths (TAFWP, PORVs and safety valves) will be recorded on Texas Instruments chart recorders.
Ran e, Sensitivit
, Ener Re onse:
10 10 p Ci/cc for Xe; i 20% 40 KeV through 1.33 MeV.
133 January 30, 1981
~
~
~
~
~
A Calibration Fre uenc and Techni e:
The calibration frequency wall be zn accordance with Technical Specification 4.1 which requires calibration of the radiation monitoring system during each refueling.
Calibration of detector to be performed remotely with a CS-137 source calibrator unit.
Vendor Model Number:
Monitorin Locations:
adjacent to each maxn valves, safety valves Eberline - Detector-SA-11 Interface-IB-4HTCC Data.Ag.Mod.-DAM-3 Isolator-CLI-1 Texas Inst.
Recorder-Tigraph 100 Intermediate Bldg. El. 298'4" steamline upstream of relief and TAFWP supply lines.
Re resentative Sam lin :
Detectors view total flow through pape.
Back round Correction:
3" Lead Shielding (iii) Location of Readouts:
Ratemeter Control Room Control Console Control Room Control Console TSC Recorders Control Room Method of Recordin Analog chart recorders/Sping-4 Control Consoles.
Data Transmission:
Shielded instrumentation cables from detectors to control room.
(iv)
(v)
(b)
The Eberline steamline monitors are compatible with the Sping-4 Control Consoles, therefore, by programming the system with the appropriate conversion factors, a
direct readout in p Ci/sec is possible.
Conversion curves have been developed which take into account the radionuclide spectrum distribution as a function of time after the onset of a loss of coolant accident, in conjunction with assumed primary to secondary leakage.
The open/clos'e status of the possible release paths (TAFWP, PORVs and safety valves) will be recorded simultaneously with the steamline activity in each main steam loop.
By integrating the flow rate and the activity concentration with respect to time, the activity released can be calculated. January 30, 1981 Assurance of Obtainin Readin s at Least Ever 15 Minutes:
Outputs are recorded continuously when zn alarm.
Source of Power:
Instrument Bus 1B (backed by emergency diesel generator).
In addition, the DAM-3 has an internal 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> battery backup.
Calculational Procedures for Obtainin Release Rates: