3F0597-11, Provides Response to NRC Requests Contained in Re Control Room Emergency Ventilation Sys & Control Complete Habitability Envelope

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Provides Response to NRC Requests Contained in Re Control Room Emergency Ventilation Sys & Control Complete Habitability Envelope
ML20141D906
Person / Time
Site: Crystal River 
Issue date: 05/15/1997
From: Hickle B
FLORIDA POWER CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
3F0597-11, 3F597-11, NUDOCS 9705200234
Download: ML20141D906 (4)


Text

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Florida.

Power CORPORATION U Yanaue*

May 15~, 1997 3F0597-11 U. S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, D.C.

20555-0001

Subject:

Control Complex Habitability Envelope

Reference:

NRC to FPC letter, 3N0497-11, dated April 8, 1997

Dear Sir:

The purpose of this letter is to provide a response to NRC requests contained in the referenced letter regarding the Control Room Emergency Ventilation System (CREVS) and the Control Complex Habitability Envelope (CCHE).

As requested by NRC, Florida Power Corporation (FPC) confirms that if breaches occur in the CCHE in excess of the allowed total breach area, as established by calculations referenced in FSAR paragraph 7.4.9, that both' trains of CREVS will be declared inoperable, and CR-3 will comply with Conditions D or E of Technical Specification LC0 3.7.12.

The Crystal River Unit 3 (CR-3) procedure., and administrative control processes applicable to operability of CCi:VS and maintaining the integrity of the CCHE are described in Attachment '..

If you have any questions, please contact the Manager, Nuclear Licensing at (352) 563-4566.

Sincerely,

$)

b- -

i B. J. Hickle, Director l

Nuclear Plant Operations BJH/SCP Attachment llllll[llll*l[!llh hll, xc:

Regional Administrator, Region II Project Manager, NRR Senior Resident Inspector CRrSTAL TWVER ENERGY COMPLEX: 15700 W Power Une St e Crystal Rker. Florida 3442S4708 e (352) 7954486 A noriaa Progress Company OAnno_

9705200234 970515 PDR ADOCK 05000302!

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j U. S.-Nuclear Regulatory Commission 3F0597-11

'Page 2 of 4 ATTACHMENT A CONTROL COMPLEX HABITABILITY ENVELOPE ADMINISTRATIVE CONTROLS The following discussion outlines the procedures and administrative control processes applicable to operability of CREVS maintaining the integrity of the CCHE.

4 CONTROL OF BREACHES CP-147, " CONTROL COMPLEX HABITABILITY ENVELOPE (CCHE) BREACHES", provides instructions for personnel discovering a CCHE breach, planning activities which will cause a breach in the CCHE, and for documenting and tracking breaches. The i

procedures described below, which perform inspection or maintenance of CCHE l

components, refer to CP-147 for actions to be taken when breaches are discovered.

The ' PERSONNEL INDOCTRINATION' section of CP-147 contains instructions to enter 2

Technical Specification (TS) LC0 3.7.12, Conditions D or E, as applicable, when breaches exist in the CCHE in excess of the allowed total breach area. Condition D is for both trains of CREVS-inoperable in Modes 1, 2, 3, or 4, and requires i

entry into TS LC0 3.0.3 immediately.

Condition E is for both trains of CREVS

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inoperable during movement of irradiated fuel assemblies and requires suspension of movement of irradiated fuel assemblies.

DOORS PM-175," CONTROL COMPLEX HABITABILITY ENVELOPE (CCHE) DOOR MAINTENANCE", provides instructions for inspection and. maintenance of CCHE doors.

This includes measuring the size of any breaches or gaps in door seals, and notifying the Nuclear Shift Supervisor of breaches.

This procedure is performed every 120 days. A computerized scheduling system provides notification of inspection due dates under this procedure.

Maintenance is performed, as necessary, based on inspection results. The CCHE door inspections are identified in the preventative maintenance scheduling system as Control Sheet (CS) 5262.

j SP-805, " SURVEILLANCE OF PLANT FIRE 000RS", directs monthly surveillance of fire l

doors throughout the plant, including the CCHE doors.

Fire protection staff perform the surveillances to verify the general condition of the fire doors. The staff, under the surveillance procedure, pays particular attention to the conditicn of CCHE door seals. Checking for breaches is stressed for CCHE doors, and notification to the Operations Shift Supervisor of their existence is required.

Performance of this procedure is scheduled through the computerized Surveillance Coordinating and Tracking (SCAT) system.

SP-805A, " ANNUAL INSPECTION OF PLANT FIRE D0 ORS", provides instructions for j

inspection of fire doors to National Fire Protection Association Standard 80-1983, " Standard for Fire Doors and Windows." This is a more rigorous inspection of fire rating aspects of doors than 5P-80f and includes instructions for identification of CCHE breaches associated with doors.

Performance of this procedure is scheduled through the computerized SCAT system.

1 4

U. S. Nuclear R:gulatory Commission 3F0597-Il

'Page 3 of 4

)lALL PENETRATIONS SP-407, " FIRE BARRIER PENETRATION SEALS", provides for inspection of penetration seals in rated fire walls. This includes the walls which make up the exterior of the CCHE.

This surveillance is performed once per 18 months, however, the penetrations are divided into ten groups with one group inspected each 18 months.

If the failure rate for the group being inspected exceeds 5%, then additional groups must be inspected until a failure rate of less than 5% is achieved.

Performance of this procedure is scheduled through the computerized SCAT system.

DAMPERS PM-139, "HVAC EQUIPMENT CHECK AND SERVICE", provides instructions for heating ventilation and air condition equipment inspection and maintenance.

This includes dampers in the control room emergency ventilation system that provide isolation of the CCHE. Specific information is provided regarding the dampers that comprise the CCHE boundary and the required actions for discovery of breaches.

Inspections of the CCHE boundary dampers are scheduled once per 24 months and are identified in the computerized preventative maintenance scheduling system as CS 5026.

Numerous procedures perform surveillance, calibration, and functional testing of the radiation and toxic gas detection systems which provide signals to close CCHE isolation dampers for CREVS operation in the recirculation mode.

SP-353, " CONTROL ROOM EMERGENCY VENTILATION SYSTEM AND RM-A5 MONTHLY TEST", performs monthly surveillance of the CREVS intake radiation monitors (gas and iodine / particulate).

The surveillance verifies that upon actuation of the monitor that the resulting output signals close the CCHE isolation dampers.

PT-368, "T0XIC GAS DETECTOR FUNCTIONAL TEST", performs monthly tests of the sulfur dioxide (50 ) and chlorine detectors monitoring the CREVS intake 1

duct.

The functional tests verify detector actuation, and that the resulting signals close the CCHE isolation dampers within the required actuation time.

PT-366, "T0XIC GAS DETECTOR SYSTEM CALIBRATION (TRAIN A)" and PT-367, "T0XIC GAS DETECTOR SYSTEM CALIBRATION (TRAIN B)", perform calibration of the 50 and chlorine detectors monitoring the CREVS intake duct.

The 2

calibration also verifies that the resulting signals close the CCHE isolation dampers within the required actuation time.

PT-373, "CR1 & 2 T0XIC GAS DETECTION SYSTEM FUNCTIONAL CHECK", performs a monthly functional ch'eck of the two 50 detectors installed in the vicinity 2

of the 50 storage tMk at Crystal River Units 1 & 2.

The functional check 2

verifies detector actuation, and that the resulting signals close the CR-3 CCHE isolation ('.ampers.

PM-273, "CRI & 2 T0XIC GAS DETECTION SYSTEM CALIBRATION", performs calibration of the two 50, detectors installed in the vicinity of the S02 storage tank at Crystal River Units 1 & 2.

The calibration procedure verifies detector actuation, and that the resulting signals close the CR-3 CCHE isolation dampers.

.y U. S. Nuclear Regulatory Commission 3F0597-11

'Page 4 of 4 FLOOR DRAINS There are two floor drains that can result in CCHE breaches if water is not maintained in the drain line loop seals. A preventative maintenance activity is established to replenish the water in the loop seals every 30 days.

This activity is identified in the computerized preventative maintenance scheduling system as CS 5295.

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