IR 05000333/1984024
| ML20128N876 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 05/28/1985 |
| From: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Glovier H POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8506030405 | |
| Download: ML20128N876 (2) | |
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MAY 2 81985
. Docket No. 50-333 Power Authority of the State of New York James A. FitzPatrick Nuclear Power Plant ATTN:
Mr'. Harold A. Glovier Resident Manager P. O. Box 41
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Lycoming, New York 13093 Gentlemen:
Subject:
Inspection Report No. 50-333/84-24 We acknowledge receipt of your letter dated April 3,1985, in response to our letter dated March 12, 1985.
Thank you for describing the actions which you have taken or plan to take to improve your post-accident sampling and monitoring capabilities. We reviewed
- your schedule for completing these actions, and we find that your completion dates are acceptable, except for the following items:
84-24-02, 84-24-06A, 84-24-06D, 84-24-08C and 84-24-10A.
Based on a telephone conversation between Mr. Eric Mulcahey of your staff and Dr. Walt Pasciak of this office on May 13, 1985, we understand that the above items will be completed by August 15, 1985. These actions will be examined during a future inspection of your licensed program.
Your cooperation with us is appreciated.
Sincerely, Original Signed By:
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Thomas T. Martin, Directo Division of Radiation Safety and Safeguards Cc:
L. W. Sinclair, President
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J. P. Bayne, First Executive Vice President and Chief Operations Officer-A. Klausmann, Vice President - Quality Assurance and Reliability R. L. Patch, Quality Assurance Superintendent George M. Wilverding, Chairman, Safety Review Committee Gerald C. Goldstein, Assistant General Counsel NRC Licensing Project Manager Dept. of Public Service, State of New York Public Document Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of New York 0FFICIAL RECORD COPY RL FITZ 84-24 - 0001.0.0 i
05/22/85-l 8506030405 850528 L
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Nuc8.ar Power Plant Po bo= 41 Lycomeng New %)rk 13093 315 342 3840 Harold A. Glovier
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4# Authority April 3, 1985 JAFP-85-0324 United States Nuclear Regulatory Commission Region I 631 Park Avenue King Of Prussia, PA 19406 Attention:
Thomas T. Martin, Director Division of Radiation Safety and Safeguards SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 INSPECTION NO. 84-24
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References:
1.
NUREG-0737, Clarification of TMI Action Plan Requirements 2.
Letter dated March 12, 1985 from T. T. Martin (NRC) to H. A. Glovier (NYPA)
Gentlemen:
In accordance with your request in reference 2, we are sub-mitting our response to each of the findings contained in the subject inspection report in Attachment I to this letter. Please note that for those findings which contain several parts, each portion has been provided with an individual designation to simplify response and tracking of the commitments made (if any)
and each finding item has been referenced to the appropriate NUREG-0737 task number.
Please contact Mr. Eric A. Mulcaheyoof the James A. FitzPatrick Nuclear Power Plant staff if you have any questions concerning this matter.
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HAROLD A. GLOVIER HAG:EAM:jaa Attachment Copy:
L. W. Sinclair, WP0 R. J. Converse, JAF J. P. Bayne, WPO R. L Patch, JAF
R. A. Burns, WPO E. Mulcahey, JAF f
J. J. Kelly, WPO NRC Resident Inspector, JAF g
G. M. Wilverding, WP0 NRCI-84-24 File
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ab J. A. Gray, Jr., WPO Document Control Center p'[%
A. Klausmann, WPO
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ATTACHMENT I
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RESPONSE TO IEE INSPECTION50-333/84-24
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NEW YORK POWER AUTHORITY
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JAMES A. FITZPATRICK NUCLEAR POWER PLANT
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April 3, 1985 JAFP-85-0324
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Attachment I Page-2-84-24-01:
Revise the procedure to assure that no dilution water is held up in the line.
Reference:
NUREG-0737,II.B.3, Post Accident Sampling Capa-bility.
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Response:
PSP-17 section 4.8.26 will be revised to repeat air injection to ensure that the water is. removed from the coolant dilution sample line.
October.1, 1985.
This will be accomplished by 84-24-02:
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Revise the procedure so that personnel are aware of the proper loading and installation of iodine / particulate filter
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assembly.
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Reference:
NUREG-0737, II.B.3, Post Accident Sampling Capa-
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bility.
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Response:
Instructions will be added. to PSP-17 delineating
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proper loading and installation of the iodin /e particulate filter as semb:Ly.
This will be accomplished by October 1,
1985.
84-24-03:
Complete provisions for the aackaging and shipment of the PASS samples to the offsite_ laboratory.
Reference:
NUREG-0737, II.B.3, Post Accident Sampling Capa-bility.
Response:
The PIM's " Post Accident Sample Cask Operation and Maintenance Manual" NUPAC PAS-1, revision 1 has been received and will be incorporated into appropriate plant procedures.
This will be accomplished by October 31, 1985.
_84-24-04:
Evaluate the adequacy of.the MCA software to adequately anal-yze a post-accident mixture of. radionuclides.
Reference:
NUREG-0737, II.B.3, Post ~ Accident Sampling. Capa-bility.
Response:
An evaluation will be performed to determine the adequacy of the MCA
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software to accident mixture of radionuclides. adequately analyze a post by November 30, 1985.
This will be accomplished
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Attachment I-
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Page-3-84-24-05A:
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Perform a time and motion study for the sampling and analysis of dissolved gas.
Reference:
NUREG-0737, II.B.3, Post Accident Sampling Capa-
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-bility.
Response:
A time and motion study for the sampling and anal-ysis of dissolved gas..will be performed within 90 days of reactor start-up from the 1985. refueling outage.
Start-up is-scheduled for May 6, 1985.
84-24-05B:
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Document the previous commitment for the sampling of dis-solved gas, including the sensitivity and -accuracy of the analytical method.
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Reference ~:
NUREG-0737, II.B.3, Post _ Accident Sampling Capa-bility.
Response:
Sensitivity and accuracy documentation of the'
analytical method for sampling dissolved gas has been pro-vided by the General Electric Company to the NRC by -January 18, 1984 to Mr. Darrell G.
Eisenhut.
This was found to be
- acceptable by Mr. William V. Johnston NRR on July 17, 1984.
84-24-06A:-
Alarm set points for the PASS background monitor should be
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revised to-reflect the specified criteria for the evacuation
.of the a,rea.
Reference:
NUREG-0737, II.B.3, Post Accident Sampling Capa-bility.
Response:
The PASS radiation monitor alarm set points will be-set to the level specified in the PASS Operating Procedure PSP-17 by October 31, 1985.
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Attachment I Page-4-84-24-06B:
Coordination should be established between the groups that
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perform the calibration of the PASS radiation monitors and audits.
Calibration should be conducted in accordance with manufacturer's recommendations.
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Reference:
NUREG-0737, II.B.3, Post Accident Sampling Capa-bility.
Response:
Radiation source calibration of the PASS radiation monitors will be coordinated between the RES and I & C de-partments.
An evaluation will be performed to determine a method for calibrating to the manufacturer's recommendations especially with regard to radiation source calibrations. This will be accomplished by November 30, 1985.
84-24-06C:
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All PASS components should be included in the formal preven-
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tive maintenance program.
Reference:
NUREG-0737, II.B.3, Post Accident Sampling Capa-bility.
Response:
A formal preventative maintenance program will in-clude PASS components recommended by the vendor to be in the program.
This will be accomplished by December 31, 1985.
84-24-06D:
Procedures should be revised to call for the installation of an Ag-Zeolite cannister during use of the PASS.
Reference:
NUREG-0737, II.B.3, Post Accident. Sampling Capa-bility.
Response:
The PASS Operating Procedure, PSP-17, will be re-l vised to require the use of silver zeolite cannisters in the L
continuous air monitor and/or low volume air sample under accident conditions.
This will be accomplished by October 1, 1985.
84-24-07A:
Evaluate the effect from the iodine / particulate plate-out on the NGEM chamber under high release emergency conditions.
i Reference:
NUREG-0737, II.F.1, ATTACHMENT 1, Noble Gas Ef-
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fluent Monitors.
Response:
An empirical calculation will be performed to evaluate the effect of iodine / particulate plate-out on the NGEM chamber under high release emergency condition ~s by L
December 31, 1985.
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Attachment I Page-5-i
_84 -24- 07B :
Evaluate the energy dependence of the factor whi h i convert exposure rate to activity release rate, since the c
s used to response of 'the ion chambers may shift energy spectrum following an accident.
to the variable due Reference:
NUREG-0737, fluent Monitors.
II.F.1, ATTACHMENT 1, Noble Gas Ef-
_ Response:
The en'ergy dependence of the factor which i to convert exposure rate to activity release s used pursued through the vendor.
rate is being information will be received by October.ticipated It is an that this point, 31, 1985 At that of the calibration._an evaluation will be performed on the appro.
priateness
_B4-24-07C:
Provide the capability for the dose assessment
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to receive the results directly from the N bl computer model Monitor.
o e Gas Effluent
_ Reference:
NUREG-0737, fluent Monitors.
II.F.1, ATTACHMENT 1,
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Noble Gas Ef-
_ Response:
The Authority disagrees with the inputting the NGEM results directly to dose assessment requirement for computer model for the following reasons: the
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Present method for inputting monitor data. procedures provide a simp reliable and rapid
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This would require a major software modificati major plant to be realized. wiring modification with little or' no cost on and a benefit (
data has been identified.No regulatory requirement for dir c.
g monitor
_84-24-08A:
iodine in the sampling line. Perform an empirical determinat
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e line loss of Reference:
NUREG-0737, Analysis 6f Plant Effluents.II.F.1, ATTACHMENT 2, Sampling and Response:
An empirical calculation will be performed to by Decemberdetermine possible line loss of iodine i 31, 1985.
n the sampling line i
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Attachment I Page-6-84-24-08B:
Revise procedures to identify sample collection, handling and transport steps under emergency conditions.
Identify antici-pated hazards and time constraints under these circumstances.
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In particular, evaluate the source term and determine expo-sure hazards and constraints to personnel from the NGEM chamber (see section 5.2.1 of this report for details).
Reference:
NUREG-0737, II.F.1, ATTACHMENT 2, Sampling and Analysis of Plant Effluents.
Response:
A study will be performed to establish the source term from the NGEM and determine exposure hazards to person-nel occupying the PASS stack sample room.
This study will be
. accomplished by December 31, 1985.
Within 90 days ' of re-ceiving the study, the PASS Operating Procedure, PSP-17, will-be revised to reflect study results, sample collection,
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handling, transport steps, anticipated hazards and time con-straints.
84-24-08C:
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Incorporate the iodine results into the source term which may be used for offsite dose assessment.
Reference:
NUREG-0737, II.F.1, ATTACHMENT 2, Sampling and Analysis of Plant Effluents.
Response:
Procedures will be revised to input plant and/or field sample data for dose assessment during an emergency.
This wi'll be accomplished by October 31', 1985.
84-24-08D:
Provide shielding for cartridge storage in the sample building to limit exposure in the event that a higher than anticipated activity is collected on a cartridge.
These items wil1~be reviewed during a subsequent inspection.
Reference:
NUREG-0737, II.F.1, ATTACHMENT 2, Sampling and Analysis of Plant Effluents.
Response: - The sampling equipment supplier will be requested to evaluate the consequences of a flow element failure.
Cor-
-rective and/or safety measure (s) shall be undertaken based upon the evaluation of the supplier's respons.
Attachment I Page-7-84'24-09A:
Define the primary and alternative methods for estimating core' damage based on reliability of data and methodology.
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Reference:
NUREG-0737, II.F.1, ATTACHMENT 3,
Containment
High-range Radiation Monitor.
Response:
The " Containment Radiation Monitoring - Post Acci-dent" procedure RTP-34 will be revised to clarify the primary and alternative methods for estimating core damage. This will be accomplished by October 31, 1985.
84-24-09B:
Assure the calibration would be valid for the modified posi-tioning of the "A" detector.
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Reference:
NUREG-0737, II.F.1, ATTACHMENT 3,
Containment High-range Radiation Monitor.
Response:
An enginet ring " evaluation will be performed prior to repositioning the
'A detector which is tentatively planned for the 1986 refueling outage.
84-24-09C:
Provide documentation to justify the present detector loca-tions are free from shielding effects or. direct dose rate effects from adjacent structures or equipment.
Reference:
NUREG-0737, II.F.1, ATTACHMENT 3,
Containment High-range Radiation Monitor.
Response:
An engineering evaluation is being performed to determine if the present detector locations are appropriate.
The evaluation will be completed by July 31, 1985.
84-24-10A:
Address sample purging and in-plant field analysis in appli-cable procedures.
Reference:
NUREG-0737, II.D.3.3, Improved Inplant. Iodine Instrumentation Under Accident Conditions.
Response: LProcedures which would be used for in-plant field air sampling / analysis in emergency situations will be re-
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viewed and revised as necessary to require iodine cartridge purging.
This will be accomplished by November 30, 1985.
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Attachment I Page-8-
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84-24-10B:
Provide readily accessible air samplers for emergeticy situa-tions.
Reference:
NUREG-0737, II.D.3.3, Improved Inplant Iodine
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Instrumentation Under Accident Conditions.
Response:" Emergency air samplers are maintained in cabinets designated for emergency use.
In addition, the RES depart-ment has plans for building an instrument issue room to control instrument location.
This will ensure a larger, readily available inventory of day-to-day instruments.
The instrument issue room is expected to be completed prior to the 1986-refueling outage.
84-24-11:
The inspector checked the preceding calibration records which
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indicated that these instruments were calibrated within -the due date.
However the above two calibration records showed that there were extremely high drift with these ex?lained problems instruments.
The licensee that the radiation instruments were calibrated independently and at different intervals by the I&C department and the radiation department.
The I&C calibration used two point electronic pulse input from a pulse generator while the radiation department cali-bration used one point radiation dose rate input for a four.
decade instrument.
In order to avoid similar problems from-recurrence, the licensee agreed to have one department in charge for the calibration and that more than one point dose rate source be used in the calibration.
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i Reference:
None, Response:
This item was responded to in item 84-24-06B.
l 84-24-12:
The instrument calibration stickers attached to the instru-j ments were not properly filled in.
The instrument numbers
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were incorrectly placed where the " Calibration Due Date"
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should be.
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None.
I Response:
Instrument calibration stickers have been replaced by properly completed stickers.
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Attachment I Page-9-
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84-24-13:
According to the licensee's PASS personnel, the normal cooling water to the sample cooler would not be available after loss of offsite power.
They stated that emergency power was available and that an " emergency water supply con-nection" was provided at the sample cooler.
However there is no defined water pump (powered by emergency bus) nor defined
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water source physically hooked up to this connection.
Reference:
None.
Response:
Preliminary evaluations indicated that sample cooling may not be required to maintain sample temperatures within the vendor's recommended temperature for the equip-ment.
Several tests will be run to determine if cooling is required.
These tests will be completed by December 31, 1985.
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