View source for 3F0687-16, Forwards Control Room Habitability Evaluation Rept.Rept Reflects Post Refuel VI Mod Outage Scheduled to Begin Sept 1987 Per NUREG 0737,Item III.D.3.4.Items from 870609 NRC Meeting Addressed

{{Adams
| number = ML20234D890
| issue date = 06/30/1987
| title = Forwards Control Room Habitability Evaluation Rept.Rept Reflects Post Refuel VI Mod Outage Scheduled to Begin Sept 1987 Per NUREG 0737,Item III.D.3.4.Items from 870609 NRC Meeting Addressed
| author name = Simpson E
| author affiliation = FLORIDA POWER CORP.
| addressee name = 
| addressee affiliation = NRC OFFICE OF ADMINISTRATION &amp; RESOURCES MANAGEMENT (ARM)
| docket = 05000302
| license number = 
| contact person = 
| case reference number = RTR-NUREG-0737, RTR-NUREG-737, TASK-3.D.3.4, TASK-TM
| document report number = 3F0687-16, 3F687-16, NUDOCS 8707070377
| package number = ML20234D892
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}

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Power C O R P oR AT1ON June 30, 1987 3F0687-16 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

==Subject:==
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG 0737, Item III.D.3.4 Control Room Habitability Evaluation Report

==Dear Sir:==

Attached is the Crystal River Unit 3 (CR-3) Control Room Habitability Evaluation Report. This report includes the follow-up discussion items from the NRC meeting of June 9, 1987.
The report was prepared to reflect the post Refuel VI modifications.                                     The CR-3 Refuel VI outage is scheduled to begin in September 1987.
The items from the June 9,1987 NRC meeting are addressed as follows:
: 1. Have ot'ner accidents other than MHA been considered in the control room habitability review?
The MHA is the bounding case for control                                      room habitability as identified in Section 4 of the report.
: 2. Has the failure of RM-A5 been considered?
(a) Address failure of detector, (b) detection by other means and (c) procedures (a) The RM-A5 monitor is equipped with alarms to alert the operator of. sample flow f ailures and detector failures.                               In addition, a detector power failure will result in actuation to recirculation..
(b) The purpose of the monitor is to detect increases' in radiation from releases other than a LOCA and to isolate the control room.
Other plant detectors provide indication of high. radiation in various areas of the plant.
8707070377 870630 PDR     ADDCK 05000302
((3 P                           PDR~
GENERAL OFFICE: 3201 Thirty fourth Street South
* P.O. Box 14o42
* St. Petersburg, Florida 33733 * (813) 866 5151 A Florida Progress Company

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l Page 2 of 3 3F0687-16 June 30, 1987 (c) Upon receipt of high radiation alarms, plant procedures require certain actions to be taken (e.g. verification of interlock actuation, or monitoring of related detectors).
: 3.                                    Has the opening of access doors been considered?
This concern is precluded by the existing fire protection and security procedures which require a watch to be posted in the event these doors need to remai n open.                                               Section 3.1.1. of the report addresses this concern.
: 4.                                    Clarify the calculated infiltration value of 333 CFM stated in the S02 report.
The 333 CFM was a preliminary value based on overly conservative parameters.                                            The actual calculated infiltration rate is 236 CFM as given in Sect. 3.3 of the report. This calculated infiltration rate confi rms the actual inleakage to be less than the analysis val ue .                                         An air filtration rate of 355 CFM (.06 air changes) was used in the habitability analyses.
: 5.                                    Provide a more detailed description of infiltration paths found and actions taken.
A comprehensive walkdown was performed on the control room envelope                                                                    j boundary.                                          The results of this walkdown are described in Section 2.2                            '
of this report.
: 6.                                    Does FPC intend to perform a one time or periodic air leakage test on the control room envelope?
FPC does not feel that one time or periodic tests are required due to the following:
l (a) The control room habitability envelope analyses conservatively                                                                     1 assume .06 air volume change per hour which is well above the calculated value.
(b)                                  The above is consistent wi th the positions stated in Murphy Campe, SRP 6.4 and Reg. Guides 1.78 and 1.95.                                                    j
: 7.                                     Provide the basis for calculations in the report to enable NRC personnel to verify results.
The requested information is provided in the attached report and the supplemental S02 report dated May 7, 1987, i
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3F0687-16                                                                                    )
June 30. 1987
: 8. Air monitoring equipment is a high maintenance item.       How are the                  I operators protected when monitors are out of service?
Proposed technical specifications Section 3.3.3.11 submitted in TSCRN 82, Attachment C dated June 22, 1983, identified required actions to be taken in the event these monitors are unavailable.
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Sincerely,    ,
E. C. Simpson, Director                                                                      J Nuclear Site Support EMG/sdr Attachments xc: Dr. J. Nelson Grace Regional Administrator, Region II Mr. T. F. Stetka Senior Resident Inspector i
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