Text

Revision 01 to RA-EP-02865, Emergency Plan Off Normal Occurrence Procedure
	ML16131A668
Person / Time
Site:	Davis Besse
Issue date:	04/30/2016
From:	Tyrie R; FirstEnergy Nuclear Operating Co
To:	; Office of Nuclear Reactor Regulation
References
	RA-EP-02865
	Download: ML16131A668 (19)
	v • d • e

FE NOC Data Date Time: 04/30/2016 08:28:1 AM D Davis-Besse Power* Statli'on Transmittal Report Page 1of1

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Unit Document Number Doc Type Sheet/Section Revision Version Change Type Change Number Document Status HC AC CD TOCl TOC2 Changes BB1 ~-EP-02865 PRGC 0000 3ft'!if4fffEilcPff Cl IAll6E APPll!9VE8 0 0 !;PQ~I DBl RA-EP-02865 PROC 0000 SIGNIFICANT CHANGE REVISED 0 0 EPON DBl RA-EP-02865 PROC 0001 SIGNIFICANT CHANGE APPROVED 1 0 0 EPON Use this document transmittal to update the identified documents and remove the superseded documents from use.

Page 1of18 Davis-Besse Nuclear Power Station EMERGENCY PLAN OFF NORMAL OCCURRENCE PROCEDURE RA-EP-02865 LOSS OF CONTAINMENT INTEGRITY REVISIONOl Prepared by: Ron Tyrie Procedure Owner: Emergency Response Manager 04/30/16 Effective Date: - - - - - - - - - -

LEVEL OF USE:

IN-FIELD REFERNCE

2 RA-EP-02865 Revision 01 TABLE OF CONTENTS 1.0 PURPOSE ........ .-............................................................................................................................ 3

2.0 REFERENCES

.............................................................................................................................. 3 3.0 DEFINITIONS .............................................................................................................................. 3 4.0 RESPONSIBILITIES .................................................................................................................... 3 5.0 INITIATING CONDITIONS ........................................................................................................ 4 6.0 PROCEDURE ............................................................................................................................... 5 7.0 FINAL CONDITIONS .................................................................................................................. ?

8.0 RECORDS .................................................................................................................................... 7 9.0 COMMITMENTS ..............................................................................................................*.......... 7 , Containment Penetration List by Penetration Location ...................................................... 8 , Containment Azimuth Overview ........................................................................................ 18

3 RA-EP-02865 Revision 01 1.0 PURPOSE 1.1 This procedure provides a method to determine the source of leakage from containment allowing isolation or other mitigation actions. Stopping or reducing radiological releases from Containment during Emergency Plan events will minimize the dose impact to the General Public and to Station Personnel.

2.0 REFERENCES

2.1 Developmental 2.1.1 Davis-Besse Nuclear Power Station (DBNPS) Emergency Plan 2.1.2 USAR Table 6.2-23, Containment Vessel Isolation Valve Arrangements 2.1.2 Condition Report 11-94552, EP Drill Improvement Opportunity for Loss of Containment Integrity 2.2 Implementation 2.2.1 NOP-OP-1015, Event Notifications.

2.2.2 NOP-SS-3300, FirstEnergy Enterprise Records Management Program.

2.2.3 RA-EP-01500, Emergency Classification 2.2.4 RA-EP-02420, Search and Rescue 2.2.5 RA-EP-02520, Assembly and Accountability 2.2.6 RA-EP-02710, Reentry 2.2.7 RA-EP-02864, Containment Evacuation 2.2.8 DB-OP-06412, Process and Area Radiation Monitors 2.2.9 DB-OP-06504, Emergency Ventilation System 2.2.10 DB-PF-03008, Containment Local Leakage Rate Tests 3.0 DEFINITIONS 3 .1 Loss of Containment Integrity - As it is used in this procedure means a condition, a failure, or a component misalignment that results in a flowpath from Containment to the Environment typically via the Auxiliary Building. This flowpath when combined with elevated containment pressure (such as following a loss of the Reactor Coolant System fission product barrier) produces leak rates that exceed the normally expected containment leakage rates causing a release of radioactive material to the environment.

4.0 RESPONSIBILITIES 4.1 The Shift Manager shall implement this procedure with the assistance of the Emergency Response Organization.

4 RA-EP-02865 Revision 01 4.2 The Emergency Director shall evaluate Fission Product Barrier Matrix as described in RA-EP-01500, Emergency Classification procedure and radiological conditions for potential Emergency Classification Upgrade and/or changes to Protective Action Recommendations.

4.3 Radiation Protection personnel shall investigate, verify and keep the Shift Manager and the Emergency Response Organization informed of radiological conditions.

5.0 INITIATING CONDITIONS 5 .1 Initiate this procedure when during Emergency Plan implementation, a loss of containment integrity may exist as indicated by one or more of the following conditions:

5.1.1 Confirmed alert and/or high area radiation monitor alarm in areas adjacent to Containment as indicated by:

a. FIRE OR RADIATION TRBL (9-1-G).

5.1.2 Confirmed fire alarm in areas adjacent to Containment as indicated by:

a. FIRE OR RADIATION TRBL (9-1-G).

5.1.3 Confirmed process radiation monitor alarm from one or more of the following:

a. CREVS TRAIN 1 RAD HI (9-1-A)

b. CREVS TRAIN 2 RAD HI (9-2-A)

c. UNIT VENT RAD HI (9-3-A).

5.1.4 Actuation of Fire Protection System caused by elevated temperatures as indicated by the following:

(9-5-G) FIRE WTR TURB BLDG PRESS LO

(9-2-G) FIRE WTR ELEC PMP ON

(9-3-G) FIRE WTR DSL PMP ON 5.1.5 Abnormal radiation levels or airborne radioactivity detected during a survey.

5 .1.6 Confirmed computer radiation alarm in areas adjacent to Containment.

5.1. 7 Unexpected lowering of Containment Pressure.

5 RA-EP-02865 Revision 01 6.0 PROCEDURE WARNING6.1 The Loss of Containment Integrity may result in the release of steam and/or radioactive material from Containment. This may adversely affect anyone in the vicinity of the release.

6.1 Evaluate the impact of the Loss of Containment Integrity event (radiation and/or high temperatures near failure point), and affected areas.

6.2 IF the decision has been made to evacuate* the affected area, THEN sound the Containment Evacuation Alarm AND make an announcement such as:

"Attention all personnel."

"Evacuate the Area and report to the Radiological Restricted Area Access Control Point. Notify your supervisor. Avoid the

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ Area."

"Evacuate the Area and report to the Radiological Restricted Area Access Control Point. Notify your supervisor. Avoid the Area."

6.3 REFER TO RA-EP-02864, Containment Evacuation, for addition guidance for evacuation of containment or areas near containment.

6.4 REFER TO RA-EP-01500, Emergency Classification, and evaluate fission product barrier matrix conditions and radiation levels for possible emergency classification upgrade.

6.5 Direct security to obtain a list of personnel in evacuated areas to determine if anyone is in the affected area.

REFER TO RA-EP-02520, Assembly and Accountability.

6.6 Assist in locating unaccounted for individuals. REFER TO RA-EP-02420, Search and Rescue as necessary.

6.7 REFER TO DB-OP-06412, Process and Area Radiation Monitors, and verify automatic or manual actions associated with alarming area radiation monitors or process radiation monitors have been completed.

6.8 Determine a likely Containment Release point as follows:

Review Fire and Radiation alarms. The Control Room Fire and Radiation CRT provides an overview that may help determine affected areas by displaying rooms with active Fire and/or Radiation Alarms.

6 RA-EP-02865 Revision 01 NOTE6.8

Radiological Conditions may cause elevated dose rate alarms that are not related to the Loss of Containment Integrity event. These alarms may be due to shine from radiological conditions in Containment.

The sequence of radiation and fire alarms may point to likely sources with the earliest alarms closest to the initial release point.

Evaluate evolutions in progress at start of release. Equipment status changes may provide indications that can be used to determine possible release point.

REFER TO Attachment 1, Containment Penetration List by Penetration Location. This attachment provides a list of penetrations sorted by plant area allowing determination of potentially affected penetrations if an impacted plant area is known. In addition, the attachment provides potential isolation points, if available, for each penetration. Penetrations marked with an* are a direct release point from Containment without further failures. For example, the failure of a Containment Vacuum Breaker Penetration (check valve AND motor operated isolation) provides a direct path from Containment.

REFER TO Attachment 2, Containment Azimuth Overview to assist in identifying leak locations by Containment Azimuth or adjacent areas.

For any area identified, review system conditions* for the systems that have containment penetrations noted in Attachment 1, Containment Penetration List by Penetration Location.

Changes in system parameters such as changes in temperatures, flows, pressures, etc. may be used to determine potentially affected systems. Isolate or remove affected systems from service to stop releases if possible.

Verify proper SFAS Actuation for the Trip Parameters present. REFER TO DB-OP-02000, RPS, SFAS, SFRCS Trip or SG Tube Rupture Table 2, SFAS Actuated Equipment AND Table 4, SFAS Actuate Equipment (Computer Points). The failure of a component to isolate may be the cause of the release.

6.9 Notify the Technical Support Center and the Operations Support Center of any suspected Containment Release points.

6.10 As determined by the Emergency Response Organization, stop or mitigate any potential release paths as follows:

6.10.1 IF an area will be reentered following evacuation, THEN REFER TO RA-EP-02710, Reentry.

6.10.2 Isolate any potential Containment release paths.

6.10 .3 Patch or establish other temporary measures to stop or reduce Containment release.

6.10.4 IF Containment Spray operation to reduce Containment airborne activity level or Containment pressure is desired, THEN REFER TO DB-OP-06013, Containment Spray System to establish Containment Spray Manual Operation (manual actuation of Containment Spray).

7 RA-EP-02865 Revision 01 6.10.5 Monitor Radiation Elements and off-site survey data to assess effectiveness of actions taken.

7 .0 FINAL CONDITIONS Potential release locations have been identified and/or compensatory measures taken to reduce the release of Radioactive Material.

8.0 RECORDS 8.1 IF the following quality assurance records are completed by this procedure during a classifiable event, THEN the records shall be processed and retained as part of the Event Package in accordance with RA-EP-02720, Recovery Organization, OTHERWISE the following quality assurance records completed by this procedure shall be listed on the Nuclear Records List, captured, and submitted to Enterprise Records Management in accordance with NOP-SS-3300:

8.1.1 None 8.2 The following non-quality assurance records are completed by this procedure and may be captured and submitted to Enterprise Records Management in accordance with NOP-SS-3300:

8.2.1 None 9.0 COMMITMENTS None

8 RA-EP-02865 Revision 01 Attachment 1, Containment Penetration List by Penetration Location Page 1of10 This Attachment lists Containment Penetrations by the Area or Room where the penetration enters Containment.

The purpose is to allow identification of potential Containment Release Paths after determining an affected area or room. Penetrations marked with an

are a direct release point from Containment without further failures.

ELEVATION 643', MAIN STEAM ROOMS 600, 601 Number Description Location Remote Isolation Drawing Reference Points 33* Containment Vessel Mai11 Steam Line Room to the CV5006 Inside M-029E Purge Inlet Line rear of the west room. CV5005 Outside 646' elevation 245° azimuth 39 Main Steam Line #2 Main Steam Line Room MS 100 Outside M-007A, M-284A from SG2 646' elevation 123° azimuth None Inside 40 Main Steam Line # 1 Main Steam Line Room MS 101 Outside M-007A, M-284A from SG 1 646' elevation 237° azimuth None Inside ELEVATION 630' CONTAINMENT ANNULUS Number Description Location Remote Isolation Drawing Reference

. Points 8C* Containment Vessel Annulus above Equipment Hatch CV5072 Outside M-029B, M-229 Vacuum Breaker -Center None Inside 630' elevation 209° azimuth 8A* Containment Vessel Annulus above Equipment Hatch CV5070 Outside M-029B, M-229 Vacuum Breaker -Far Left None Inside 630' elevation 203° azimuth 8E* Containment Vessel Annulus above Equipment Hatch CV5074 Outside M-029B, M-229 Vacuum Breaker -Far Right None Inside 630' elevation 215° azimuth 8B* Containment Vessel Annulus above Equipment Hatch CV5071 Outside M-029B, M-229 Vacuum Breaker - Second from Left None Inside 630' elevation 206° azimuth 8D* Containment Vessel Annulus above Equipment Hatch CV5073 Outside M-029B, M-229 Vacuum Breaker - Second from Right None Inside 630' elevation 212° azimuth 8H* Containment Vessel Annulus above Incore Mezzanine CV5077 Outside M-029B, M-229 Vacuum Breaker -Center None Inside 630' elevation 151° azimuth 8F* Containment Vessel Annulus above Incore Mezzanine CV5075 Outside M-029B, M-229 Vacuum Breaker -Far Left None Inside 630' elevation 145° azimuth 8J* Containment Vessel Annulus above Incore Mezzanine CV5079 Outside M-029B, M-229 Vacuum Breaker -Far Left None Inside 630' elevation 157° azimuth

9 RA-EP-02865 Revision 01 Attachment l, Containment Penetration List by Penetration Location Page 2of10 ELEVATION 630' CONTAINMENT ANNULUS - continued Number Description Location Remote Isolation Drawing Reference Points 8G* Containment Vessel Annulus above Incore Mezzanine CV5076 Outside M-029B, M-229 Vacuum Breaker - Second from Left None Inside 630' elevation 148° azimuth 81* Containment Vessel Annulus above Incore Mezzanine CV5078 Outside M-029B, M-229 Vacuum Breaker - Second from Right None Inside 630' elevation 154° azimuth ELEVATION 603', ELECTRICAL PENETRATION ROOM 1 Number Description Location Remote Isolation Drawing Reference Points 73A* Containment # 1 EPR 603 Level CV2002B Outside OS-33F Pressure Sensor None Inside RPS-SFAS Ch 3 73C* Containment to #1EPR603 Level CV645B Outside OS-33F Annulus Af>

None Inside 73B* CTMT Air Sample # 1 EPR, 7 ft. high, 2 ft. from the CV5011C Outside M-029B, FSK-M-(CTMTDome) shield building wall. CV5010C Inside HCB-38-4, FSK-M-610' elevation 235.5° azimuth HCB-38-15, FSK-M-HCB-38-16, FSK-M-HCB-38-17, FSK-M-HCB-38-18, FSK-M-HCB-38-28 102* Electrical #1 EPR, along the shield building None-ensure M-019, Manual E-25Q-Penetrations wall. Nitrogen is 396, Manual E-25Q available 5, E-370, E-371 ELEVATION 603', ELECTRICAL PENETRATION ROOM 2 Number Description Location Remote Isolation Drawing Reference Points 34* Containment Vessel #2 EPR toward the rear 14 'high CV5006 Inside M-029E Purge Inlet Line near the ceiling along the shield CV5005 Outside building wall.

617' elevation 78° azimuth 72A* Containment #2 EPR 603 Level CV2001B Outside OS-33F Pressure Sensor None Inside RPS-SF AS Ch 2 72C* Containment to #2 EPR 603 Level CV624B Outside OS-33F Annulus ~p None Inside 101* Electrical #2 EPR, along the shield building None - ensure M-019, Manual E-25Q-Penetrations wall. Nitrogen is 396, Manual E-25Q available 5, E-370, E-371

10 RA-EP-02865 Revision 01 Attachment l, Containment Penetration List by Penetration Location Page 3of10

ELEVATION 603', SPENT FUEL POOL AREA Number Description Location Remote Isolation Drawing Reference Points 82* Equipment Hatch Spent Fuel Pool Area 603 Level None CB&I Drawing #25, 603' elevation 209° azimuth Manual C-37-217-1 23*. Fuel Transfer Tube Spent Fuel Pool Canal Transfer SFl Outside - M-035, C-254 1-2 Pit Reach Rod 570.75' elevation 170° azimuth (Flange Inside)

(East Tube) 24* Fuel Transfer Tube Spent Fuel Pool Canal Transfer SF2 Outside - M-035, C-254 1-1 Pit Reach Rod 570.75' elevation 176° azimuth (Flange Inside)

(West Tube)

ELEVATION 603' OR 585' AIRLOCKS 80* Emergency Airlock Outside None M-029B, CB+I 589'elevation 315° azimuth Drawings #100, #152,

164, #200, and #248, Manual C-3 7-217-1 81* Personnel Airlock Auxiliary Building 603 None M-029B, CB+I 603' elevation 130° azimuth Drawings #100, 164, 152, 200 and 248, Manual C-3 7-217-1 ELEVATION 585' MECHANICAL PENENTRATION ROOM 3 Number Description Location Remote Isolation Drawing Reference Points 36 Auxiliary #3MPR AF608AND OS-17A SH. 1 Feedwater Train 1 EF3 ** Outside OS-62 Line to SG 1 None Inside 71A* Containment #3 MPR 585 Level CV2000B Outside OS-33F Pressure Sensor None Inside RPS-SFAS Ch 1 59* Secondary Side #3 MPR at the top comer on the None M-007 A, M-229 Chemical Cleaning Shield Building wall, by missile Flange Outside Line shield. Flange Inside 594' elevation 251° azimuth 37 Main F eedwater #3 MPR Rear of Room FW601 Outside M-007A, M-284B Line to SG 2 594' elevation 77° 50' azimuth None Inside

- EF3 is on the Emergency Feedwater line to the Auxiliary Feedwater line.

11 RA-EP-02865 Revision 01 Attachment l, Containment Penetration List by Penetration Location Page 4of10 ELEVATION 585' MECHANICAL PENENTRATION ROOM 3- continued Number Description Location Remote Isolation Drawing Reference Points 26* Containment Spray #3 MPR toward the rear. CS1530 Outside M-034, M-234B, M-Air Test Line 598'elevation 251.5° azimuth None Inside 234C, FSK-M-HCB (Train 1) 1, FSK-M-JBD-10-55, FSK-M-JBD-10-56 71B* Containment Air #3 MPR, 4' high, left of annulus CV5011A Outside M-029B, FSK-M-Sample (Top of door. CV5010A Inside HCB-38-1, FSK-M-West D-ring) 589' elevation 210° azimuth HCB-38-19, FSK-M-HCB-38-20, FSK-M-HCB-38-21, FSK-M-HCB-38-28 71C Core Flood Tank 1- #3 MPR, chest high by the pipe CV1544 Outside M-034, FSK-M-FCB-1 Fill and Nitrogen chase. None Inside 1-3, FSK-M-FCB-1-6, Supply Line 589' elevation 210° azimuth FSK-M-FCB-7-2 ELEVATION 585' MECHANICAL PENENTRATION ROOM 4 Number Description Location Remote Isolation Drawing Reference Points 2 SG 1 Secondary #4MPR SS607 Outside OS-51 Sheet 2 Water Sample Line None Inside 18 SG 2 Secondary #4MPR SS598 Outside OS-51 Sheet 2 Water Sample Line None Inside 35 Auxiliary #4MPR AF599 Outside OS-17A SH. 1 Feedwater Train 2 None Inside Line to SG 2 3 CCW Supply to #4MPR12" diameter piping CC1411A Inside, . M-036C, M-040D, M-CTMT approx. 12 ft. high, CC 141 lB Outside 236D, M-236E, M-lOft. inside MPR4. 236E, J-1029 SH. 1 597' elevation 159° azimuth 43B* Containment Vessel #4 MPR 2 ft. above the catwalk. CV5011E Outside M-029B, FSK-M-Air Sample Return

593' elevation 144° azimuth None Inside HCB-39-1, FSK-M-(Train 1) HCB-39-3 74A* Containment #4 MPR 585 Level CV2003B Outside OS-33F Pressure Sensor None Inside RPS-SFAS Ch 4 17* Containment Vessel #4 MPR 8" pipe on shield CV343 Outside M-029B, M-229 Leak Test Line building wall toward the rear of (Flange Inside)

4MPR 597' elevation 110.5° azimuth 42B* Containment Vessel #4 MPR above catwalk, left of CV5010E Outside M-029B, FSK-M-Air Sample Return the annulus door None Inside HCB-39-7, FSK-M-(Train 2) 597' elevation 144° azimuth HCB-39-2

12 RA-EP-02865 Revision 01 Attachment l, Containment Penetration List by Penetration Location Page 5of10 ELEVATION 585' MECHANICAL PENENTRATION ROOM 4 - continued Number Description Location Remote Isolation Drawing Reference Points 67* Hydrogen Dilution #4 MPR above the catwalk. CV5090 Outside M-029D, M-229, FSK-System Supply Line 593' elevation 147° azimuth None Inside M-HBC-73-6 4 CCW Outlet Line #4 MPR Approx. 7' high and 1O' CC1407A Inside M-036C, M-040D, M-fromCTMT insideMPR4 CC1407B Outside 236D, M-236E, M-593' elevation 159° azimuth 236F, J-1029 SH. 1 42A Station Air Supply #4 MPR at center column by pipe SA2010 Outside M-015D, FSK-M-Line chase None Inside HBB-9-1, FSK-M-597' elevation 144° azimuth HBB-9-2, FSK-M-JBD-11-5 43A Instrument Air #4 MPR at center column by pipe IA2011 Outside M-015A, FSK-M-Supply Line chase None Inside HBB-10-1, FSK-M-593' elevation 144° azimuth HBB-10-2, FSK-M-JED-5-1 47B Core Flood Tanks MPR4, under the catwalk. CF1542 Outside M-034, FSK-M-FCB-Vent Valve 593' elevation 153° azimuth CF5A and CF5B 10-3, FSK-M-FCB-9-6, Inside FSK-M-FCB-9-1, FSK-M-FCB-9-2, FSK-M-FCB-9-3, FSK-M-FCB-9-4, FSK-M-FCB-9-5 5 Containment Air #4 MPR at SW Supply Lines to SW1366 Outside OS-20 SH. 1 Cooler SW Inlet CACs None Inside Line 6 Containment Air #4 MPR at SW Supply Lines to SW1368 Outside OS-20 SH. 1 Cooler SW Inlet CACs None Inside Line 7 Containment Air #4 MPR at SW Supply Lines to SW1367 Outside OS-20 SH. 1 Cooler SW Inlet CACs None Inside Line 9 Containment Air #4 MPR at SW Supply Lines to SW1356 Outside OS-20 SH. 1 Cooler SW Outlet CACs None Inside Line 10 Containment Air #4 MPR at SW Supply Lines to SW1358 Outside OS-20 SH. 1 Cooler SW Outlet CACs None Inside Line 11 Containment Air #4 MPR at SW Supply Lines to *SW1357 Outside OS-20 SH.1 Cooler SW Outlet CACs None Inside Line 68B* Containment Air #4 MPR floor level, 10 ft. left of CV5010B Outside M-029B, FSK-M-Sample (Reactor annulus vent door 308A under CVSOl lB Inside HCB-38-7, FSK-M-cavity) cs 19. HCB-38-8, FSK-M-593' elevation 140° azimuth HCB-38-9, FSK-M-HCB-38-10, FSK-M-HCB-38-26, FSK-M-HCB-38-27

13 RA-EP-02865 Revision 01 Attachment l, Containment Penetration List by Penetration Location Page 6of10 ELEVATION 585' MECHANICAL PENENTRATION ROOM 4 - continued Number Description Location Remote Isolation Drawing Reference Points 68A Pressurizer Quench #4 MPR floor level, by the ladder SS235A Outside M-040A, FSK-M-Tank Sample Line for the 'catwalk left of the annulus SS235B Inside HCB-26-1, FSK-M-door. HCB-26-2, FSK-M-593' elevation 140° azimuth HCC-43-2 74C Pressurizer #4 MPRjust past the black CAC DH2736 Outside M-033A, M-033B, M-Auxiliary Spray SW pipes. DH2735 Inside 033C, M-230B, M-593' elevation) 10.5° azimuth 233D SHI, FSK-M-CCB-10-1, FSK-M-CCB-10-2, FSK-M-GCB-10-4 1 Pressurizer Sample #4 MPR middle of Catwalk RC240A Inside, M-030A, M-042C, Line 597' elevation 150° azimuth RC240B Outside FSK-M-CCB-17-1, FSK-M-CCB-17-2, FSK-M-CCB-11-3 38 Main F eedwater #4 MPR Rear of Room FW612 Outside M-007A, M-284B Line to SG 1 595' elevation 246° azimuth None Inside 74B* CTMT Air Sample #4 MPR, approximately 2 ft. CV5010D Outside M-029B, FSK-M-(Top of East D- from the floor, just past the black CV5011D Inside HCB-38-3, FSK-M-ring) SW pipes. HCB-38-11, FSK-M-593' elevation 110.5° azimuth HCB-38-12, FSK-M-HCB-38-13, FSK-M-HCB-38-14, FSK-M-HCB-38-26 47A Core Flood Tanks #4 MPR, below the catwalk CF1545 Outside M-034, FSK-M-FCB Sample Line 593' elevation 153° azimuth CF2A and CF2B 1, FSK-M-FCB-3-6, Inside FSK-M-FCB-3-5, FSK-M-FCB-3-3, FSK-M-FCB-3-2, FSK-M-FCB-3-4, FSK-M-FCB-3-1 25* Containment Spray #4 MPR, left of the annulus door CS1531 Outside M-034, M-234D, M-Air Test Line 597'elevation 140° azimuth None Inside 233B, FSK-M-GCB (Train 2) 1, FSK-M-HCB-4-1, FSK-M-JBD 55/FSK-M-JBD-10-57 12 CCW Supply to #4 MPR, one foot above the CC1567A Inside M-036C, M-236E, J-Control Rod Drive catwalk. CC1567B Outside 1029 SH. 1 Mechanisms 589' elevation 150° azimuth

14 RA-EP-02865 Revision 01 Attachment l, Containment Penetration List by Penetration Location Page 7 of IO ELEVATION 565' MECHANICAL PENENTRATION ROOM 1 Number Description Location Remote Isolation Drawing Reference Points 28 Low Pressure #IMPR DRIB Outside OS-004 SH. 1 Injection Train 1 None Inside 56 Reactor Coolant #I MPR behind the Boronometer MU38 Outside M-03 IB, FSK-M-CCB-Pump Seal Water 578'elevation 216° azimuth MU59A-D Inside 11, FSK-M-CCB Return 19, FSK-M-CCB-7-20, FSK-M-CCB-20-1, FSK-M-CCB-20-5, FSK-M-CCB-20-6, FSK-M-CCB-20-13, FSK-M-CCB-20-16, FSK-M-CCB-20-18, FSK-M-CCB-33-4, FSK-M-CCB-34-3, FSK-M-HCC-3-1, 14 Letdown Line to #I MPR behind the boronometer MU2Alnside M-03 IA, M-23 IA, M-Purification cage approx. 2-3 ft. high. MU3 Outside 23 IB, FSK-M-CCB Demins. 578.5' elevation 203.5° azimuth* 1, FSK-M-CCB-9-2 22 High Pressure #I MPR right hand side over HP2D Outside M-031C, M-033A, M-Injection Line pipe chase to ECCS 1-1. (HP49 Manual 23 IE, M-233D, M-Stop Check 233E Inside) 50 High Pressure #I MPR right hand side over MU6421 Outside M-031C, M-033A, M-Injection Line pipe chase to ECCS 1-1. HP2C Outside 23 IE, M-233D, M-(HP48 Manual 233E Stop Check Inside) 21 Demineralized * #I MPR toward the rear of the DW683 IA Inside M-OIOC, M-210E, M-Water Supply Line room at about knee level. DW6831B 210H 578.5' elevation 239.5° azimuth Outside 49 Refueling Canal Fill #1 MPR, behind Boronometer None-Manual M-033B, M-233G, M-Line 578.5' elevation 200° azimuth Valves Only 235B DH87 Outside DH88 Inside 52 Reactor Coolant #I MPR, behind the MU66A Outside M-03 IB, FSK-M-CCB-Pump 2-1 Seal Boronometer (MU242 Manual 8-1, FSK-M-CCB-8-2, Water Supply 578.5' elevation 214° azimuth Stop Check FSK-M-CCB-13-7, Inside) FSK-M-CCB-14-4 53 Reactor Coolant #I MPR, behind the MU66B Outside M-03 IB, FSK-M-Pump 2-2 Seal Boronometer (MU243 Manual CCB-8-1, FSK-M-Water Supply 578.5' elevation 214° azimuth Stop Check CCB-8-2, FSK-M-Inside) CCB-13-6,

'FSK-M-CCB-14-3

15 RA-EP-02865 Revision 01 Attachment l, Containment Penetration List by Penetration Location Page 8of10 ELEVATION 565' MECHANICAL PENENTRATION ROOM 1 - continued Number Description Location Remote Isolation Drawing Reference Points 54 Reactor Coolant # 1 MPR, behind the MU66C Outside M-03 lB, FSK-M-CCB-Pump 1-1 Seal Boronometer (MU244 Manual 8-10, FSK-M-CCB Water Supply 578.5' elevation 210° azimuth Stop Check 11, FSK-M-CCB-8-19, Inside) FSK-M-CCB-13-4, FSK-M-CCB-14-1 55 Reactor Coolant #1 MPR, behind the MU66D Outside M-03 IB, FSK-M-Pump 1-2 Seal Boronometer (MU245 Manual CCB-8-10, FSK-M-Water Supply 574' elevation 210° azimuth Stop Check CCB-8-11, FSK-M-Inside) CCB-8-19, FSK-M-CCB-13-5, FSK-M-CCB-14-2 69* Hydrogen Dilution # 1 MPR, Piping is attached to a CV5065 Outside M-029D, M-229, M-System Supply Line small motor and blower on the None Inside 229A left toward the rear.

574' elevation 234.5° azimuth ELEVATION 565' MECHANICAL PENENTRATION ROOM 2 Number Description Location Remote Isolation Drawing Reference Points 27

Low Pressure #2MPR DHlA Outside OS-004 SH. 1 Injection Train 2 None Inside 29 Decay Heat Suction #2MPR DH1517 AND OS-004 SH. 1 Line DHl518 Outside DHl 1 Inside 44B CTMT N2 Supply #2 MPR 1-inch yellow pipe, NN23 6 Outside M-019, FSK-M-HBB-Header approx. 9' high and 8' inside #2 None Inside 14-1, FSK-M-HBB MPR. 2, FSK-M-HBD-206-578.5' elevation 125° azimuth 19, FSK-M-HBD-423-1 13* Containment Vessel #2 MPR About 15' inside room DR2012A Inside M-046, M-246A, FSK-Normal Sump Drain along south wall. DR2012B Outside M-HBC-9-2, FSK-M-574' elevation 135.5° azimuth HBB-2-1 16 Containment Vessel #2 MPR about knee high along RCl 719A Inside M-040A, M-240C, M-Equipment Vent the shield building RCl 719B Outside 240D Header 578.5' elevation 132° azimuth 41 Pressurizer Quench #2 MPR approximately 15' inside RC232 Outside M-040A, FSK-M-Tank Circulation the room. None Inside HCC-89-2, FSK-M-Inlet Line 574' elevation 125° azimuth HCC-86-3, FSK-M-HCC-86-2, FSK-M-HCC-86-1, FSK-M-HCB-7-1, FSK-M-HCB-7-2

16 RA-EP-02865 Revision 01 Attachment l, Containment Penetration List by Penetration Location Page 9of10 ELEVATION 565' MECHANICAL PENENTRATION ROOM 2 - continued Number Description Location Remote Isolation Drawing Reference Points 19 High Pressure #2 MPR inside door on wall, HP2A Outside M-031C, M-033A, M-Injection Line valves are about 15' high (HP57 Manual 231E, M-233D, M-578.5' elevation, 128.5° azimuth Stop Check 233E Inside) 20 High Pressure #2 MPR inside door on wall, MU6422 Outside M-031C, M-033A, M-

Injection Line valves are about 15' high HP2B Outside 231D, M-233D, M-578.5' elevation, 128.5° azimuth (HP56 Manual 233E Stop Check Inside) 57 SG 2 Blow Down #2 MPR near Wet Layup Recirc MS603 Outside OS-008 SH. 3 Line Pump None Inside OS-008 SH. 5 60 SG 1 Blow Down #2 MPR near Wet Layup Recirc MS611 Outside OS-008 SH. 1 Line Pump None Inside OS-008 SH. 3 51* Hydrogen Purge #2 MPR on high catwalk. CV5038 Outside M-029D, M-229, M-System Exhaust 574.5' elevation 121.5° azimuth None Inside 229B, M270, FSK-M-HJBC-73-7, FSK-M-HBC-F60 ELEVATION 565' TOP OF FUEL TRANSFER TUBE AREA- ROOM 221 44A Core Flood Tank 1- Above the fuel transfer tubes, CF1541 Outside M-034, FSK-M-FCB-2 Fill and N2 less than 1 ft. above the floor. None Inside 7-1, FSK-M-FCB-1-1, Supply Line 578.5' elevation 125° azimuth FSK-M-FCB-1-2, FSK-M-FCB-1-5, FSK-M-FCB-1-4 ELEVATION 565', MAKEUP PUMP ROOM Number Description Location Remote Isolation Drawing Reference Points 32 Reactor Coolant MU Pump Room just past the RCl 773A Inside M-040A, M-240A, M-System Drain Line Emergency Sump Valves RCl 773B Outside 240C to R.C. Drain Tank 566' elevation 159° azimuth 48 Pressurizer Quench MU Pump Room, past the RC229A Outside M-040A, M-240B Tank Circulation Emergency Sump Valve cutouts, RC229B Inside Outlet Line on the Shield Building wall at the floor level.

566' elevation 162° azimuth

17 RA-EP-02865 Revision 01 Attachment 1, Containment Penetration List by Penetration Location

. Page 10of10 ELEVATION 545', #1 EMERGENCY CORE COOLING ROOM Number Description Location Remote Isolation Drawing Reference Points 30* CTMTVessel #1 ECCS Pump Room Toward DH9B Outside M-033C, M-283 Emergency Sump the rear at ceiling level. None Inside Recirc Line 561'elevation 148° azimuth 31* CTMTVessel #1 ECCS Pump Room Toward DH9A Outside M-033C, M-283 Emergency Sump the rear at ceiling level. None Inside Recirc Line 561'elevation154° azimuth

18 RA-EP-02865 Revision 01 Attachment 2, Containment Azimuth Overview Page 1of1 This Attachment provides approximate Containment Azimuth values (bolded degree values) as well as an overview of areas adjacent to Containment.

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