ML19340E080

Forwards Response to NRC 801031 Request for Status of Efforts Re Implementation of TMI Lessons Learned Requirements & Request for Info Re NUREG-0737 Items

ML19340E080
Person / Time
Site:	Calvert Cliffs
Issue date:	12/30/1980
From:	Poindexter C BALTIMORE GAS & ELECTRIC CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML19340E081	List: ML19340E080 ML19340E083
References
RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.D.1 NUDOCS 8101060333
Download: ML19340E080 (27)

Text

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.Q December 30N1980 __

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CHRis H. POINDEXTER 48 E*1 vice enEsiotNT ENGsNEER NG AND CONSTRUCTsoN Mr. D. G. Eisenhut, Director Division of Licensing I

Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission I

Washington, D. C.

20555

Subject:

Calvert Cliffs Nuclear Power Plant 2

Units Nos. 1 & 2, Dockets Nos. 50-317 & 50-318 Resoonse to NUREG-0737 i

References:

(a) Letter from D. G. Eisenhut to All Licensees of Operating Plants and Applicants for Operating f

Licenses and Holders of Construction Permits i

dated October 31, 1980; NUREG-0737 (b) Letter from A. E. Lundvall, Jr. to D. G.

Eisenhut dated December 15, 1980 f

Dear Mr. Eisenhut:

Reference (a) required documentation reflecting the status of our efforts related to TMI Lessons Learned. The enclosures to this letter are a submittal in response to reference (a) with exceptions as noted in reference (b), addressing items due to the NRC by January 1,1981.

i' We have referenced our prior submittals wherever appropriate to minimize duplication. References are identified for each item addressed.

If any additional information is required, we vould be pleased to provide i

it to you.

BALTIMORE GAS AND ELECTRIC COMPANY 1

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Vice Presi8ent i

Engineering and Construction STATE OF MARYLAND:

TO WIT:

CITY OF BALTIMORE:

l Mr. C. H. Poindexter being duly sworn states that he is Vice President of the Baltimore Cas and Electric Company, a corporation of the

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Mr. D. G. Eisenhut Tage 2 December 30, 1930 State of Maryland; that he executed the foregoing Response for the purposes therein set forth; that the statements made in said Response are true and correct to the best of his knowledge, information and belief; and that he was authorized to execute the Response on behalf of said corporation.

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J. A. Biddison, Esquire G. F. Trowbridge, Esquire Mr. E. L. Conner, Jr. - IiRC G

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Shift Technical Advisor (STA)

EEFEEENCES:

(a) Letter frcm A. E. Lundvall, Jr., to D. G. Eisenhut dated December lh, 1979 (b) Letter frem A. E. Lundvall, Jr., to D. G. Eisenhut dated November 10, 1980 Our current STA program is as described by reference (a) and its associated references. Modified Technical Specifications regarding the STA requirement were submitted by reference (b). The STA training progrem is as described in attachments (1), (2), (3) and (h). All persons fulfilling the en-shift requirement associated with cur STA prcgram have ecmpleted the described training as of December 12, 1980.

We currently plan to continue with the present STA progrsm until such time as NRC guidance (as mentioned under the " clarification" paragraph of this item) is published which woul:1 allow a phase out of STA's based upcn upgraded qualificaticns for Shift Supervisors and an improved centrol rocm man-machine interface.

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Current Shift Technical Advisor Training Program The Baltimore Gas and Electric Ccmpany has chosen, with ITRC concurrence, to staff the Shift Technical Advisor position with licensed senior reactor operators. These cperators do not possess an accredited degree, but rather have been extensively trained in aspects of nuclear power plant cperation and analysis which meet and exceed the requirementa of the IIRC letters dated Septenber 13, 1979 signed by Mr. D. G. Eisenhut and October 20, 1979 signed by Mr. H. R. Denton. This training begins with the lessons administered as part of the Calvert Cliffs Hot License Training Program. Several of the portiens of the ccurse, such as Mathematics, Reactor Physics, Chemistry, and Reactor Operations are equally applicable to an STA cr a licensed SRO.

Similiarly related tcpics covered as part of the Licensed Operator Requali-fication Program would provide portions of the STA retraining program.

Descripticns of the subjects covered in Hot License Training and License Operator Requalification Program are included as attachments 2 and 3 In addition to the license training mentioned above the Shift Technical Advisors attended formal training in subjects pertinent to their assigned duties. These courses were administered by college professors er consultants with at least a Bachelor of Science degree. Portions of the general technical education phase were accedited courses. The participants are being awarded 2h credits from Charles County Cc::= unity College. The STA training program was administered between February and December 1980.

GEITERAL TECHITICAL EDUCATICII:

Contact Heurs Mathematics 40 Trigonometry; Analytical Gecmetry; College Algebra; Vector analysis; Elementary Calculus, through integration and differentiation of first order equations mysics 80 Classical mysics includir he Laws of Conservation of Mass, Energy and Monen.

Nuclear Physics, Reactor mysics Chemistrv 16 Inorganic chemistq; Corrosien yrocess; Chemistry control Materials 16 Metals used in the plant and their properties Reactor Thermodynamics and Heat Transfer 160 Heat transfer fundamentals; Laws of Thermodynamics; Gas Laws; Equations of State; Use of Steam Tables; Core Thermal Characteristics; Thermal & Hydraulic Transient Response

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I.A.l.3 Shift Manning Administrative procedures have been drafted to implement the position regarding overtime set forth by the UUREG 0737 It is expected that these procedures will be implemented prior to February 1,1981.

II.B.2.

Plant Shielding Syste=s considered in our anakysis for plant shielding include all those listed NUREG 0737 with the exception of the of the chemical and volume control system (CVCS), the waste gas system, and the shutdown cooling systen. As noted in our letter (A.E. Lundvall, Jr. to D.G. Eisenhut) dated January 4,1980, CVCS and waste processing systems isolate en a safety injection actuation signal (SIAS).

Core damage,and therefore the release of radioactivity, would not occur before ecnditions actuate safety injectica. Any desired cooling would be acccmplished via one of the two steam generators vice the shutdown cooling system.

II.D.l.

Relief and Safety Valve Testing "As a sponsor of the EPRI WR Safety and Relief Valve Test Program, Baltimore Gas and Electric Company intends the comply with the requirements of NUREG 0578, Item 2.1.2.

By letter dated December 15, 1980, R.C. Youngdahl of Ccnsumers Pcwer Company has provided the current PWR Utilities' positions en NUREG 0737, Item II.D.l. clarificaticns. Briefly those positions are:

A.

Safety and Relief Valves and Piping - the EPRI " Program Plan for Performance Testing of WR Safety and Relief Valves," Revisien 1, dated July 1,1980, dces provide a program that satisfies the NRC requirements. Discussien with the NRC staff and their consultants are resolving specific detailed issues.

B.

Block Valves - The EPRI Program has not formally included the testing of block valves. However, a small number of block valves have been tested at the Marshall Steam Station Test Facility. The WR Utilities and EPRI cannot provide a detailed block valve test program until results of the Wyle and CE relief valve tests are available. Therefore, a block valve test program will not be provided before July,1981.

The WR Utilities and EPRI believe that the proper cperation of the TMI-2, and Crystal River block valves and other operational experience, plus knowledge of the Marshall tests, support a less hurried and more rational approach to block valve testing.

C.

ATWS Testing - PWR Utilities ~will not support additional efforts for ATWS valve testing until regulatory issues are resolved. The major safety and relief valve test facility-(CE) is nearing completion and some measures were taken to provide additional test capability beyond j

the current program requirements. The NRC should recognize that results from the current program are likely to provide most of the information i

necessary to address ATWS events (i.e., relief capability at high pressures)."

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II.E.h.2. (5)

Centainment Pressure Setpoint The current centain=ent pressure setpoint is 4 psig. The reportable containment pressure by technical specifications for Calvert Cliffs Daclear Power Plant is 1.8 psig. To this value,1 psi will be added to allcw for instrumentation un-certainties in pressure measurement, and a new containment isolation signal (CIS) setpoint of 2.8 psig shall be established. The setpoint change shall be i=plemented by July 1, 1981.

II. K.3.17 ECCs system outages Attachment (5) provides a listing of ECCS equipnent cutages which recuired ccrrective acticn. These cutages were all reported by the Licensee Event Repcrts referenced in these listings.

ATTACHEffr (5)

DOCKET NO. 50-317 EVENT LENGTil 0F LER #

DATE OUTAGE COMPONENT CAUSE 75-02 01/09/75 1 llour SIAS Logic Failure of the pressurizer pressure portion of the A-1 Module A-1 dual function logic module 75-05 01/12/75 1 flour SIAS Logic Failure of the pressurizer pressure portion of the B-7 1

Module B-7 dual function logic module 75-09 01/16/75 1 flour SIAS Logic Failure of the pressurizer pressure portion of the B-9 Module B-9 dual function logic module A

75-19 02/15/75 1 Ilour ilPSI Ileader Found to have its main drive gear loose on its shaft Iso. Valve 75-20 02/16/75 3 llours SIAS #11 Burned contacts in the ESFAS relay A-7, "B" contacts Componen t were dirty Cooling Pump t

76-08 03/05/76 30 Minutes llPSI Motor operated valve failed to operate because of blown control circuit fuse 76-31 06/21/76 15 Minutes

1. 12 Cntml Tighten a leaking nipple on its seal water line 5

Spray Pump 76-36 07/29/76 4 llours DG #12 Jacket cooling water system became air bound i

45 Minutes 76-39 08/07/76 4.72 liours DG #11 A cold solder connection on a lead to the ERA relay caused the malfunction

DOCKET NO. 50-317

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EVENT LENGTH OF LER #

DATE OUTAGE COMPONENT CAUSE 76-47 10/15/76 21 flinutes DG #12 Blown fuse on ventilation controller 76-48 11/17/76 38 Hours Safety Inj.

Torque switch had burned contacts 35 Minutes Aux. IIP Loop

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Iso. Valve 4

77-03 11/18/77 5 Hours DG #12 Controller coil was replaced 17 Minutes 77-39 05/15/77 5 Hours DG #12 Dirt on the fan main breaker contacts was the cause 45 Minutes of the failure 77-51 06/01/77 11 lleurs DG #11 Replace missing flange bolts on the scavenger air 10 Minutes blower discharge piping. Also replaced two bolts providing support for the turbo charger 77-52 06/03/77 1 Hour DG #12 Two ferruled type fittings at the inlet to cylinders 45 Minutes

1. 2 & #6 had apparently vibrated loose and required tightening 77-53 06/17/77 1 Hour DG #11 Number 6 cylinder relief valve had vibrated loose and 55 Minutes fallen off 77-54 06/22/77 2 Hours

1. 12 Cntmt Repair a leaking cooler 28 Minutes Spray Pump 77-64 07/11/77 8 Hours DG #11 Small fire on the hot exhause manifold when lube oil 10 Minutes sprayed from lube oil starter 9

DOCKET NO. 50-317 EVENT LENGTH OF LER #

DATE OUTAGE COMPONENT CAUSE 77-65 07/13/77 48 Hours DG #11 Isolation valve to the jacket coolant pressure switches was found shut 77-91 09/21/77 2 Hours DG #12 Maintenance personnel incorrectly assumed that the 40 Minutes pressure switch could be replace without affecting diesel generator availability 77-96 10/03/77 DG #11 Same as below 77-101 10/04/77 8 Hours DG #12 The service water supply control valve was observed 43 Minutes to be controlling improperly in the automatic node 77-104 10/10/77 4 Hours DG #12 Two loose fuse holders were found in the excitation 38 Minutes circuitry 77-119 11/16/77 4 Hours DG #12 Minor fuel oil, lube oil, and cooling water leaks

.25 Minutes developed 77-122 11/15/77 9 Hours DG #12 Minor fuel oil, lube oil, and cooling jack of water 33 Minutes leaks developed 78-06 01/23/78 Not given LPSI Pump GE Mange-Blast circuit breaker Type AMH 4.76.2500-00 was missing a screw 78-12 02/13/78 2 Hours SI Tanks The calibration procedure of the level transmitter.

Did not use the actual densities of the gas / fluid in the reference and variable legs.

DOCXET NO. 50-317 i

4 EVENT LENGTil 0F 1.ER #

DATE OUTAGE COMPONENT CAUSE 78-19 04/10/78 4 llours DG #12 The control valve failed to open due to its positioner 78-20 04/13/78 50 Minutes DG #11 A start / failure alarm was displayed on #11 DG. Number 4

11 DG was subsequently started successfully twice.

78-25 04/10/78 13 Minutes DG #12 At 1:52 started DG had an oversped trip. At 2:05 restarted and tested successfully.

78-34 07/08/78 58 Minutes SIAS Logic Failure of logic module. Module was replaced and Module B-8 tested satisfactorily.

78-58 12/18/78 21 Hinutes DG #11 "B" phase overload was found to be tripped and was 4

reset.

79-10 03/21/79 1 llour ECCS Pump Airline tubing did not fit snugly on the air line 42 Minutes Rm Exhaust fitting.

Fan 2

i 79-15 05/07/79 15 Minutes LPSI Pump Pump was supplying shutdown cooling.

It was stopped for 15 minutes.

79-17 05/15/79 54 llours DG #12 Blower failure 9 Minutes 1

79-28 07/24/79 z72 Hours DG #11 Generator exciter potential transformer T-54 was found to have a grounded primary winding

DOCKET NO. 50-317 EVENT LENGTH OF LER #

DATE OUTAGE COMP 0NENT CAUSE 79-37 08/28/79 24 Hours 1 ECCS & 1 CNTMT SI-4143-MOV was shut Spray System 79-46 08/27/79 8 Hours HPSI Hdr #12 Voluntarily entered to repair a cracked weld on a 48 Minutes

& #13 Chg Pumps reducer for the sample line pipe 79-48 09/14/79 68 Hours

1. 12 Cntmt Spray Motor stator coil had chafted against the incoming 25 Minutes Pump phase lead 79-56 10/01/79 4 Hours DG #11 Investigation of voltmeter showed AC calibrating series 35 Minutes resistor had come out of tolerance and was causing meter to indicate 900 volts higher 79-60 10/20/79 47 Hours DG #12 The injectors were found to be clogged and out of 40 Minutes adjustment.

79-65 11/13/79 2 Hours DG #12 Sludge deposits on governor assembly 47 Minutes 79-68 11/27/79 1 Hour DG #12 Replace an automatic vent valve on the service water 20 Minutes return line 79-69 11/17/79 7 Hours DG #11 Repair a fuel line leak 15 Minutes 79-73 12/04/79 1 Hour DG #11 The breaker auxiliary switch was found to be binding 47 Minutes and would not return to the open position.

DOCKET NO. so-317 EVENT LENGTH OF LER #

COMPONENT CAUSE DATE OUTAGE e.*

79-74 12/04/79 5 llours DC #12 Various flare and ferrule fittings loose from vibration of diesel were tightened 80-01 01/04/80 4 Hours 12A IIPSI Valve found opening 5% full travel.

Investigation Loop Stop revealed a loose termination (high resistance) on one of the electrical leads terminating at valves torque switch 80-10 02/02/80 15 Minutes DG #11, SIAS failed to fully reset before diesels were

1. 12, #21 stopped, causing a start failure alarm 80-28 05/15/80 5 ilours DG #12 Open circuit of the speed switch caused the starting 55 Minutes circuit to time out, initiating starting failure 80-32 07/01/80 19 Ilours SW Valve Saltwater Valve failed to open fully 45 Minutes

1. 5212 80-33 07/02/80 6 Hours Cntmt

1. 14 Cntmt Cooler weald not shift speed to slow 35 Minutes Cooler 80-36 07/21/80 31 Minutes

1. 11 DG

1. 11 DG no voltage or speed control 80-37 07/30/80 2 Hours

1. 11/12 DG

1. 11 & #12 DG seismic tubing required 35 Minutes 80-42 08/06/80 1 Hour ESFAS Ch ZE Channel deenergized for trouble shooting Deenergized

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DOCKET N0. 50-318

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COMPONENT CAUSE DATE OUTAGE e.*

75-29 04/02/75

1. 21 DG Speed Control Transformer opened 75-31 04/11/75 Safety Injection Safety Injection Valve would not open fully, loose Valve electrical connections 75-39 06/12/75 ESFAS Both Logic Cabinets Al & BL blacked out of system, Logic bad review of STP's 75-46 07/22/75 1 llour

1. 21 DG Breaker faulty 30 Minutes 76-02 08/18/76

1. 21 DG Speed switch shorted 76-04 11/11/76 IB SIAS Dual logic actuation module failure 76-18 12/15/76 1 Hour

1. 21 DG Corrosion clogged air starting equipment 15 Minutes 77-20 02/22/77

1. 21 DG Air start system, check valve was dirty and stuck 77-23 03/17/77 54 llours

1. 12 DG Electrical overload for ventilation fan tripped 77-28 03/22/77 13 llours

1. 21 DG Service water inlet valve leaked, low Jacket cooling 36 Minutes water

DOCKET NO. 50-318 EVENT LENGTH OF LER #

COMPONENT CAUSE DATE OUTAGE 77-47 06/21/77 5 Hours

1. 21 DG Repair minor fuel leak 77-48 06/01/77 2 Hours Testing and Aligning AC power not tested within 30 flinutes one hour.

77-54 07/18/77 5 Hours

1. 21 DG Repair Leak 77-62 08/22/77 Tri Sodium TSP insufficient TSP in Containment. Less than 75 ft Phosphate 77-63 08/26/77 Tri Sodium TSP settled in baskets.

Insufficient TSP in Containment Phosphate 77-65 08/25/77 8 Minutes Isolation Maintenance-#21 Containment Spray Header inoperable Valve 77-70 09/28/77 Tri Sodium Recalculation of the amount of TSP required in Cntmt Phosphate 77-80 11/01/77 26 Hours

1. 21 DG Minor flaintenance 55 Minutes 77-83 11/04/77 4 Hours Pressure Faulty Tramation fbdel #230lT to Voltage Signal 20 Minutes Transmitter (ESFAS)

Isolator 77-87 11/15/77 Safety Injection Safety injection Valve MOV-627 would not open because of Valve limit switches

DOCKET NO. 50-318 EVENT LENGTH OF LER #

COMPONENT CAUSE DATE OUTAGE e.*

77-91 11/25/77 72 Hours

1. 21 DG Maintenance to repair inlet control valve 77-93 12/13/77 18 Iours SI Ileader Header pressure peaked at 1475 psig when pump 35 Minutes started

~

78-02 01/10/78 72 Ilours

1. 21 DG Loss of field and reverse power relays 78-04 02/13/78 SI Tank Level Pressure used in calibration'was. incorrect Transmitter 78-07 01/18/78 Si Tank Boron concnetration below minimum 78-15 06/06/78 15 flours

1. 21 DG liigh resistance in breaker contact 30 Minutes 78-16 06/09/78 ESFAS Actuation Testing failed E/E Convertor on ESFAS Cabinet Channel 78-17 06/26/78 SI Tank Change in recalibration of level transmitter, caused tank to be overfilled 78-25 08/01/78 3 llours

1. 21 DG Service Water valve failed to open due to worn 25 Minutes plunger in solenoid 78-31 09/07/78 1 llour SI Tank Leak of reactor coolant past SIT check valve. SIT Valve Boron concentration reduced

DOCKET N0. 50-318 EVENT LENGTH OF LER #

COMPONENT CAUSE DATE OUTAGE 78-32 09/05/78 8 Hours Safety Injection Operator's error SIT 21B level greater than 199" 30 flinutes Tank 78-33 09/24/78 20 Minutes Safety Injection Signal Instrument Level Indicator 12" out of Tank calibration 78-35 10/17/78 2 Hours Shutdown Cooling Air leaked into SDC system. Loss of shutdown System cooling 78-41 11/15/78 25 Minutes Refueling Water Rad Chem Technician failed to close sample valve Tank R4T low 78-47 12/13/78 25 Minutes Refueling Water Tnk Erroneous readingk. LIA 4142 out of calibration Level Indicator RWT low level 78-48 12/13/78 50 Minutes Safety Injection Minor valve leak.

1. 22B SIT low pressure Tank 79-08 02/08/79 30 Minutes Safety Injection Fill valve not shut tight.

1. 22B SIT level low Tank 79-09 02/26/79 30 Minutes Saltwater Valve 2-CV-5209 valve remained open and throttling is done by 2-CV-5210 79-14 03/28/79-2 Hours Safety Injection Leakage through 2-CVC-269. Low level #21B SIT Tank Valve

DOCKET fl0. so_31n E "

L LER #

COMPONENT CAUSE DATE O AE e.*

79-17 05/25/79 10 Minutes

1. 21 DG Remote start button cannot be used with LSB energized 79-19 05/25/79 19 Ilours SIAS Logic flodule would not activate SI AS module B-8 47 Minutes 79-20 06/02/79 20 Minutes Safety Injection Leak valve, low level on #220- SIT Tank 79-23 06/21/79 20 Minutes

1. 21 DG Engine oil pressure switch left isolated 79-34 09/14/79 5-7 Days

1. 12 & #21 DG llangers installed on air start system non-seismic 79-37 10/05/79 1 Ilour ESFAS Logic ESFAS cabinet deenergized, sensors remained operable 10 tiinutes 79-38 10/22/79 3 Minutes SI Valve Accidental removal of Pressure Transmitter

1. E31 79-39 10/24/79 2 Hours

1. 12 & #21 DG Seismic supports being analyzed 79-40 10/12/79 2 Hours

1. 21 DG Voltage regulator overheated-replaced 79-41 10/17/79

1. 22 HPSI

1. 22 IIPSI seal failure, loss of boration path

DOCKET NO.

50-318 EVENT LENGTH OF LER #

COMPONENT CAUSE DATE OUTAGE e.*

79-42 11/27/79 5 Hours ESFAS Prz Press Transmitter out of calibration by novement of pipe Prgstgre Trans-80-01 02/25/80 7 Hours LPSI Pump LPSI removed for maintenance. Maintenance removed wrong 30 Minutes pump 80-02 01/07/80 4 flours Indicator Alarm Defective equipment, RWT low LED faulty Circuit 80-03 01/10/80 5 llours

1. 21 DG Normal maintenance 35 Minutes

'8'-11 02/27/80 46 Ilours

1. 21 DG Defective governor 0

50 liinutes 80-16 03/03/80 46 Hours

1. 21 DG Defective governor 40 Minutes 80-17 03/17/80 2 flours

1. 22 SW/SRW Taken out of service to repair tube leak 10 Minutes lleat Exch.

80-21 03/18/80 5 Ilours SI AS Faulty

1. 23 SW Pump did not start 50 Minutes Output Relay 80-23 04/16/80 3 llours ESFAS 15V DC 15 Volt power supplies overvoltage relay tripped 55 Minutcs Power Supply 80-35 07/30/80 1 llour

1. 21 DG Diesel generator taken out of service due to non-seismic 25 Minutes tubing

DOCKET N0. 50-318 EVENT LENGTH OF LER #

COMPONENT CAUSE DATE OUTAGE e.*

80-36 07/29/80 38 Minutes ESFAS Channel Replace CIS Bistables Deenergized 80-44 09/26/80 40 Minutes ESFAS SGIS Signal Isolator Failed E/E Module 80-51 11/01/80 8 Hours

1. 21 Cntmt Cooler Shorting Block in Cntmt Cooler controller 26 Minutes t

e II.

3 30 Fmall Ereak ICCA Methods We will not be prepared to address the secpo and schedule for revision of the small break IDCA model until after the results of LCPI test L3-6 have been analyzed. We expect to provide IEC with the scope and schedule by April 1, 1981.

III.D.3.h Centrol Rocm Habitability Study 4

A cen+,rol recm habitability study in acecrdance with ITJREG 0737 has been ec=pleted. We cencluded that control roc = operators are adequately protected from the effects of accidental release of toxic and radioactive gases. To facilitate review of this section, the following table identifies specific references for each item of Attachment 1, Secticn II.D.3.h., Enclosure 3 to

rJREG 0737.

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RFJZRE' ICES FOR CCICROL RCCM HABITA3ILITY EVALUATICU (a) Calvert Cliffs nuclear Pcwer Plant Final Safety Analysis Report.

(b ) Letter frem A. E. Inndvall, Jr. to R. W. Reid dated April lo, 1978;

Subject:

' Doses to Control Recm Operaters Following a Design Basis LCCA.

(c) Letter frem A. E. Inndvall, Jr. to R. W. Reid dated November 20, 1978; came subject.

(d) Centrol Rocm Habitability Study for Calvert Cliffs Unclear Pcwer Station, prepared for BG&E by Bechtel Power Corpcration, as amended (Attachment 1),

dated Ncvember 1980 and revised December 1960.

(e) Attachment 2 (1) Centrol-rocm mode of operation, i.e., pressurizatien and filter recirculation for radiological accident isolation er chlorine release-Ref. (a) Section 7.6.2 and 9.8.2 3, and Ref. (b)

(2) Control-rect characteristics (a) air volume centrol room -Ref. (b)

(b) control-room emergency zone (control rocm, critical files, kitchen, washroom, computer room, etc. ) -Ref. (a) Secticns 7.6.2 and 9 8.2.3, Ref. (6) and Ref. (c)

(c) centrol-rocm ventilation system schematic with ncM and emergency air-flow rates. -Ref. (a) Figure 9-20 (d) infiltraticn leakage rate. -Ref. (b) and Ref. (c)

(e) high efficiency particulate air (HEPA) filter and charecal adscrber efficiencies. -Ref. (b)

(f) closest distance between centainment and air intake. -Ref. (c) and Ref. (d)

(g) laycut of centrol rect, air intakes, containment building, and chlorine, er cther chemical storage facility with dimensicns.- Ref. (d) and Ref. (a)

Figures 1 - 8 and 1 - 12 (h) control-rocm shielding including radiation streaming frce penetraticns, doors, ducts, stairways, etc. -Ref. (e)

(1) automatic isolation capability-damper closing time, damper leakage and area. -Ref. (b)

(j) chlorine detecters or tcxic gas (local or remote) -Ref. (d)

(k) self-centained breathing apparatus availability (number)-Eef. (d)

(1) bottled air supply (heurs supply) -Eef. (d)

(m) emergency food and potable water supply (how many days and how many people) - Ref. (d)

(n) centrol-recs personnel capacity (normal and emergency) -Eef. (d)

(o) potassium iodide drug supply-Ref. (2)

(3) Onsite storage of chlorine and other hazardcus chemicals -Ref. (d)

(a) total amount and size of container (b) closest distance frem centrol-roca air intake (4) Offsite manufacturing, storage, er transportaticn facilities of hazardous chemicals. - Ref. (d)

(a) identify facilities within a 5-mile radiuu; (b) distance frc= centrol recm (c) Taantity of hazardous chemicals in one container (d) frequency of hazardous chemical transpertation traffic (truck, rail, and barge)

(5) Technical specificaticns (refer to standard technical specificatiens) -Ref. (b) and Ref. (d)

(a) chlorine detecticn system (b) centrol-room emergency filtrr. tion system including the capability to maintain the centrol-rocm pressurization at 1/8-in. water gauge, veri-fication of isolation by test signals and damper closure times, and filter testing requirements.

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