ML19309E829
| ML19309E829 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/20/1980 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 3--3-A-3, 3-0-3-A-3, NUDOCS 8004240467 | |
| Download: ML19309E829 (4) | |
Text
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me Florida Power C O R PO M A T 40 N April 20, 1980 File:
3-0-3-a-3 Mr. Robert W. Reid Chief Operating Reactors Branch #4 U.S. Nuclear Regulatory Comission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72
Dear Mr. Reid:
On February 15, 1980, Florida Power Corporation submitted a response concerning its implementation of NUREG-0578, Short-term Lessons Learned Recommendations, and the Comission's January 2,1980 Show Cause Order.
Since that time we have had several discussions with Mr. Chuck Long of the NRC staff concerning our response.
At the request of Mr. Long, Florida Power Corporation hereby submits the attached additional infor-mation regarding our implementation of NUREG-0578.
If you have any further questions regarding this submittal, please con-tact this office.
Very truly yours, FLORIDA POWER CORPORATION g*
P P. Y. Baynard Manager Nuclear Support Services PYBemhM01D59 800.4240467 General Office 320i Tn rty-tourtn street soutn. P O Box 14042, St Petersburg. Florda 33733 e 813-866 5151
STATE OF FLORIDA COUNTY OF PINELLAS P
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Y. Baynard states that she is the Manager, Nuclear Support Services of Florida Power Corporation; that she is authorized on the part of said company to sign and file with the Nuclear t
Regulatory Comission the information attached hereto; and that l
all such statements made and matters set forth therein are true and correct to the best of her knowledge, information and belief.
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Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 20th day of April,1980.
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LLmi Notary Public Notary Public, State of Flor.ida at Large, My Commission Expires: August'8, 1983 M
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ADDITIONAL IflFORMATION REQUESTED BY THE NRC REGARDING NUREG-0578 Item 2.1.3.a - Direct Indication of Power-operated Relief Valve and Safety Valves for PWRs:
Florida Power Corporation is participating with Babcock & Wilcox in a generic program to environmentally qualify the valve monitoring equipment.
This program is presently scheduled to be completed by October, 1980.
Should there be any change in the schedule of this program, we will notify you inmediately.
Item 2.1.3.b - Subcooling Meter:
The Tsat meter as presently designed has two hot leg and two cold leg temperature inputs.
The T at meter is powered directly from a s
vital bus and not through the Ntil system.
In addition to the above temperature inputs, FPC is also providing i
the hottest of 5 core exit T/Cs to each Tsat meter.
These T/Cs are selected from each core quadrant and the central region.
This addition will give the operator the capability to selectively ob-serve saturation margin of the hottest T/C', Th or Tg against pres-sure in either loop.
The alarm on reduced saturation margin will be from the hottest temperature input and selected loop pressure.
Installation of the modification is scheduled to be completed by June 1, 1980.
Item 2.1.5.a - Dedicated Penetration for External Recombiners or Post-Accident Purge Systems:
Crystal River Unit 3 has a redcWnt method of pressurizing the Reactor Building (RB) for 2,-Accident Hydrogen Purging (FD-302-722) by using the Statio:
ur System with valve SAV-51 in the open position (see FD-302-271, FSAR Figure 9-16).
This redun-dant system (SA) was successfully used to purge the RB following our February 26, 1980 incident.
This additional system has a flow rate of 100-150 cfm which is consistent with our purging rates.
The Station Air System and the flydrogen Purge System provide a re-dundant means for Post-Accident purging and satisfy the single-failure criteria of NUREG-0578.
Item 2.1.6.a - Integrity of Systems Outside Containment Likely to Con-tain Radioactive Material for PWRs and BWRs:
Leak rate testing of the Decay lleat System, Reactor Building Spray System and the Liquid Sampling System will be completed during our present refueling outage.
The leak rate values measured for these systems will be submitted to the NRC per NUREG-0578.
PYBemhM01059 i
P Design Review of Plant Shielding and Environmental Item 2.1.6.b Qualfication of Equipment for Spaces / Systems Which May Be Used in Post-Accident Operations.
In our January 11, 1980 submittal, we identified certain modifica-tions necessary to resolve post-accident access problems to certain plant areas. Also included in our response were tables identifying equipment locations, radiation-sensitive materials within these locations, and the integrated dose calculated for the location.
Prior to June 1, 1980, FPC will identi fy any unacceptable com-ponent/or material for mechanii.al equipment within these areas and provide our proposed corrective action to solve the problem.
For material in electrical components, this evaluation is being ac-complished as part of our review of I.E. Bulletin 79-01B.
As stat-ed in our April 17, 1980 letter to Mr. J. P. O'Reilly, this effort will be completed by June 30, 1980.
Following completion of this effort, we will provide a list of the unacceptable components /or material for electrical equipment to you along with our proposed corrective action.
Item 2.1.8.b - Increased Range of Radiation Monitors.
In addition to the procedures identified in our February 15, 1980 submittal for quantifying plant releases from potential release points, steam line monitors are required per the NRC.
These moni-tors will be provided for each steam generator on the steam line upstream of the mainsteam safety and atmospheric dump valves.
The monitors will be located outside containment and will have a local readout.
The detectors will be provided with circuitry which provides local first-out alarm indication of a significant tube leak to identify the affected steam generator.
The development of this sytem has been undertaken by FPC, with assistance from our consultant, Applied Physics Technology (APT).
An installation target date of June 1,1980 has been identified and delivery connitment dates have been requested from suppliers.
Al-though we have not received any firm commitment dates, no items have been identified as implementation restrictions.
If any item becomes a restraint to our June 1,1980 installation deadline, we will notify you innediately and provide compensatory measures until this modification can be completed.
Item 2.1.8.c - Improved In-Plant Iodine Instrumentation Under Accident Condiitions.
A portable G-M detection and counting system as identified in our February 15, 1980 submittal will be located in the Coritrol Room and Technical Support Center.
We are' also planning the use of either a portable Cadmium Telluride -
or. Sodium Iodide Detection System, coupled to a single-channel i
analyzer.
One of these portable systems will be located in both the Control Room and the Technical Support Center.
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