ML19318A888
| ML19318A888 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/20/1980 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| 3--3-A-3, 3-0-3-A-3, NUDOCS 8006240326 | |
| Download: ML19318A888 (4) | |
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M Power CORPGAAIION June 20, 1980 File: 3-0-3-a-3 Mr. Robert W. Reid Chief Operating Reactors Branch 14 U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit No. 3 Docket No. 50 's02 Operating License DPR-72 NRC Letter Dated February 29, 1980 Requesting Additional Information on Containment Furge and Vent System
Dear Mr. Reid:
By letter dated February 29, 1980, you requested additional information for Containment Purge and Vent System for Crystal River Unit 3.
This letter responds to questions la, Ib, Id, and if of the subject letter.
Florida Power Corpc.' ' ion is currently working on the required responses to questions Ic a:.m le.
In their letter of June 5,1980, B&W revised the completion date of their work from June 16, 1980 to June 30, 1980.
Therefore, Florida Power Corporation expects to submit these responses no later than July 15, 1980.
Should you have any questions concerning this subject, please contact this office.
Very truly yours, FLORIDA POWER CORPORATION "r? An~<
Patsy Y. Baynard Manager Nuclear Support Services Lobo (R04)D1 8006240 3 M General Office 3201 Thirty.iourin street soutn. P O Box 14042. St Petersburg Florida 33733 813--866-5151
O STATE OF FLORIDA COUNTY OF PINELLAS
. P. 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 Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of her knowledge, information and belief.
nYW
-A f /A. Bdyrfard Subscribed and sworn to before me, a Notary Public in and for the State and County above named, this 20th de-of June,1980.
Notary Public Notary Public, State of Florida at Large,
~My Commission Expires: August 24, 1983 CrockettNotary (D12)
FLORIDA POWER CORPORATION'S RESPONSF TO NRC QUESTIONS ON CONTAINMENT PURGE AND VENT SYSTEM Question la:
Discuss the provisions made to ensure that isolation valve closure will not be prevented by debris which could potentially become en-tranced in the escaping air and steam.
Response
The purge supply valve is protected from debris by the ductwork connected to it on the inside of the Reactor Building.
This duct-work extends downward through the refueling floor.
The duct open-ing is 48 inches wide and is sufficient to insure an equal pressure relationship across the duct wall preventing duct collapse.
The purge exhaust valve inside the Reactor Building is protected from debris by an 18" duct extension and wire mesh screen.
The short length of this duct extension insures pressure equalization across the valve.
Question Ib:
Discuss the provisions made for testing the availability of the isolation function and the leakage rate of the isolation valves, individually during reactor operation.
Response
A test to determine the availability of the isolation function of the valves will be perfonned every month, as delineated in the CR-3 Surveillance Procedure SP-335, " Radiation Monitoring Instrumenta-tion Functional Test". Also, to determine the leakage rates of the isolation valves, provisions are made in the CR-3 Surveillance Pro-cedure SP-179, " Containment Leakage Test - Types B and C".
This test is performed semiannually.
Question Ic:
Specify the amount of containment atmosphere released through the purge and vent isolation valves, for a spectrum of break sizes, during the maximum time specified for them to close in your techni-
- cal specification.
Response
Response to this question will be provided on or before July 15, 1980.
Lobo (R04)D1 e
0 FLORIDA POWER CORPORATION'S RESPONSE TO NRC QUESTIONS ON CONTAINMENT PURGE AND VENT SYSTEM (Cont'd)
Question Id:
Provide an analysis to demonstrate the acceptability of the provis-ions made to protect structures and safety-related equipment, e.g.,
fans, filters, and ductwork, located beyond the purge system isola-tion valves against loss of function from the environment created by the escaping air and steam.
Response
The fans, filters and ductwork of the Purge System (supply and exhaust) located beyond the isolation valves are not safety-related and therefore are not relied upon to mitigate an accident.
It is doubtful that pressurization of these components would cause any damage beyond the bulging of ductwork.
The Purge Exhaust charcoal filter was purchased to safety-related requirements; although, it is not a safety-related comn,nent.
These requirements include pressure criteria which insure filter integrity.
Any leakage of radioactive contaminated air / steam from the Purge Exhaust would be filtered via the Auxiliary Building Exhaust System (which includes charcoal filters).
Question le:
Provide an analysis of the reduction in the containment pressure resulting from the partial loss of containment atmosphere during the accident for ECCS back pressure determination.
Response
Response to this question will be provided on or before July 15, 1980.
Question If:
Specify the allowable leak rates of the purge and vent isolation valves for the spectrum of design basis pressures and flows against which the valves must close.
Response
The maximum closure times specified in the FSAR against design pressure and flow are 2 sec. on the outside valves and 5 sec. on the inside valves.
These closure times have been verified at CR-3.
Therefore, the allowable leakage rate is che rate in the full closed position.
This allowable leakage rate, determined in accordance with the Technical specifications, is 2500 standard cubic centimeters per minute.
Lobo (R04)D1