ML17083A316
| ML17083A316 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 04/18/1980 |
| From: | Crane P PACIFIC GAS & ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16340A918 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8004220692 | |
| Download: ML17083A316 (68) | |
Text
REGULATORY IN ORMAT ION DISTRIBUTION SYSTEM (RIOS)
ACCESSION NBR:8004220692 OOC ~ DATE: 80/04/18 NOTARIZED: NO DOCKET ¹ FACIL' Diablo Canyon Nuclear Po~er Plant< Unit 1E Pacific Ga 05000275 50"323 ahlo Canyon Nuclear Power PlantE Unit 2E Pacific Ga 05000323 AU ~ AUTHOR AFFILIATION CRANEEP ~ AD Pacific Gas 8 Electric Co ~
I REC P ~ NAME REC IP IENT AFFILIATION DENTONEH ~ RE Office of Nuclear Reactor Regulation
SUBJECT:
Reissues Revision 2 to response to NUREG 0578,Also Forwards modified instructions for Revision 2 insertion into manual eight administrative procedures previously sent to review grOup. OVerSiZed draWinqS enCl.
DISTRIBUTION CODE: BOOTS COPIES RECEIVED:LTR MERCI. ~ SIZE:~J TITLE: PSAR/FSAR AMDTS and Re 1'a ted Carr espondence C.
&~~~I NDTEB, MES c.+m m ~~
IENT
~~ ~+~1~~~& ++
T'fCIP COPIES RECIP IFNT H wc w COPIES ID CODE/NAME LTTR ENCL ID CODE/NA IE LTTR ENCL ACTION: 05 PMB SMCWw < ~ 1 AD W~ a-~n- 0 BC
~
4-~~ M l 1 1
0 LA ~~~~1
)
1 1 0 INTERNAL: 01 G FILE 1 02 NRC PDR 1 1 06 I L E 3 08 OPERA l.IC BR 1 1 09 GEOSCIEN BR 4 10 GAB 1 1 11 MECH ENG BR '
12 STRUC ENG BR 1 1 13 MATL ENG BR 2 15 REAC SYS BR 1 1 16 ANALYSIS BR 17 CORE PERF BR 1 1 18 AUX SYS BR 1 19 CONTAIN SYS 1 1 20 I L C SYS BR 1 21 POWER SYS BR 1 22 AD SITE TECH 1 26 ACCDNT ANLYS 1 1 27 EFFL TRT SYS 1 28 RAO ASMT BR 1 1 29 KIRK@ODD 1 AD FOR ENG 1 0 AD PLANT SYS 1 AD REAC SAFETY 1 0 AD SITE ANLYS IS 'DIRECTOR NRR 1 0 HYDRO METEOR BR l2 MPA 1 0 OELD 1 EXTERNAL: 03 LPDR 1 04 NSIC 1 1 30 ACRS 10 10
~pa 2g;gg TOTAL NUEEoER OF COP IFS REQUIR>> 0: LTTR g6
~r< ENCL Pf
PA.C I P I C GAS A.ND Z LZ C T RI C C 0 M PA.KT QDQ S~P 77 BEALE STREET, 31ST FLOOR ~ SAN FRANCISCO, CALIFORNIA 94106 ~ (416) 781.4211 OIL~ E1T L HLLAICE Cowkeo J. HCOLNNtY MALCOLM H. FUR BUSH OLEI N WElf 41 DLN 01AV ~ ON LU ~ Soot VICC OOCTIOCNT AND OCNCOAL CDIINCCL April 18, 1980 40 ~ ELN I KELLY HowAAOV, Solo ~
JANET 0 LOO ~ OON 10 ~ E1T L, 00100N JACE t, tkLLNI 41
~ teekeo 4 DELLA~ LNTA 40 ~ NUA OAA LEV Jo ~ 1 ~ N 0, CNOL ~ AT, 41, ROBCRT OHI BACH ~ EIEA W, HLN ~ CHEN TNE0001E L LII OSCAO 41 Ao ~ EAT L, Hk11I ~
t AISNAAO LOCLC ATSOCIATC OCNCAAl CDVNSCL DOUSLA ~ A Doi.t ~ Sv DAVIS L I,UOVIO~ ON
~ ENIOS COUNSEL CHAR LCS T. VAN 0CVSCN DAHO w, Al OEA CON J, STIES ~ LUNOAATNEA DIANA ~ E A 0 NAY ~ C N STEVEN 1 ~ U ~ Et PHILIP A. C RAN C, II R, LE%ON 0 Ck ~ SIOV ALN~ IA Cllkt'LELLE HELINEA 0 CI ~ SNA AUSSEY DLINE~
HCNRY II LAPLANTC ~ 1%AN ~, 0tl TON HICNAEL 0 Dt ~ NA1AI~
OL1'I 1 CNCINA~
WILLIAI 0 COWAAOS JOHN S SISSON
~ Dol LLO D CSICE ~ ON JOAN H TALC NLT1ICE 0 OOLOEN DAVIS 0 OILSELT ARTHVR L. HILLMAN,IIR. 4ULN H JATO t Aol kLolAUL EINE1 KESNIT 0 KU ~ I'IE HE1 ~ 1 C LI~ SON C HARL CS W. THISSCLL NL1evw LSNO 41 JOHN A. lOW SAULA Y HLN ~ A, K%11 LICK~ N Sit DANICI C. OISSON 10SELT ~, IACLtwek>> AICI4AAO E. AIEI~ 1 AIC Ikeo H HOS ~ AOOE ~ 4, ~ ETE1 ~
AEIOTANT CteteAL COUNSti. J HICNLELAEIOENSLCN 10 ~ I ~ T 0 AIOEETT IY01 C, SAN SON ~ I IAIEVA,Skeote ~ ON SUC ANN LCYIN ~ CNltt 40 ANN Swkttt1 4LCEW SI UCE LOUI ~ 0 VS%CENT DAVIS 4 WILLILNSON OI I ~ LCV* Woo
~ SUCE 0 WOSTNINOTON ttNNETN YLNO k TT 0 1 N t T ~
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, Maryland 20014 Re: Docket No. 50-275 Docket No. 50-323 Diablo Canyon Units 1 and 2
Dear Mr. Denton:
PGandE is forwarding 20 additional copies of Revision 2 to "Pacific Gas and Electric Company Response to NUREG-0578:
Short Term Lessons Learned Requirements" by courier to Mr. Mike Williams at his request,. The original Revision 2 copies were received by Mr. Williams in an incomplete condition.
The attached revised instructions have been modified to allow proper entry of Revision 2 into a manual currently updated to Revision 4 (the current revision). In addition, the Rev. 2 pages changed by subsequent revisions have been removed.
The original Rev. 2 instruction sheet has been included for your reference and use..
Eight Administrative Procedures were transmitted to the review group for their review, in the same shipment with the original Rev. 2 submittal. In case these procedures were also missing or incomplete, twenty additional copies are also being included with this shipment. ~(
c%
JQ LI JL 6 0042 00
[~
lr
)
N I
Mr. Harold R. Denton, Director April 18, 1980 Kindly acknowledge receipt of this material on the enclosed copy of this letter and return addressed envelope. ll it to me in the enclosed Attachments
ap REVISED INSTRUCTIONS FOR REVISION 2 REISSUE INSTRUCTIONS'FOR INSERTION OF NUREG-0578 RESPONSE REVISION 2 PAGES
- l. Replace the Rev. 0 pages indicated below with Rev. 2 pages:
III B 14'II V 4I" III 10'II AA 1 Z ~
- 2. Replace the Rev. 1 pages indicated below with Rev. 2 pages:
III-B-5, III-L-4, III-EE-l.
- 3. Add the Rev. 2 pages indicated below:
III-Z-llthrough III-Z-28, III-AA-2 through III-AA-4, III-NN-1 through III-NN-13, III-00-1 through III-00-19, III-PP-1 through III-PP-6 REVISED INSTRUCTIONS FOR REVISION 2 REISSUE Toe(<0:A Contml 8 Soc3 />told Date of Doctime ~
,'th h 4$
INSTRUCTIONS FOR INSERTION OF NUREG-0578 RESPONSE REVISION 2 PAGES
- 1. Replace the Rev. 0 pages indicated below with Rev. 2 pages:
I-A-2, III-B-14, III-V-4, III-Z-10, III-AA-l.
- 2. Replace the Rev. 1 pages indicated below with Rev. 2 pages:
IA lp I A3p I A4p III B5p III L4p III EE lo
- 3. Add the Rev. 2 pages indicated below:
III-Z-llthrough III-Z-28, III-AA-2 through III-AA-4, III-NN-1 through III-NN-13, III-00-1 through III-00-19, III-PP-1 through III-PP-6 .
Section 2.1.1 (Continued) heaters be available to each emergency power train within 60 minutes after a blackout. A review of several pressurizer heat loss calculations has resulted in the minimum heater requirements without offsite power of 150 Kw. These capacities will conservatively cover heat losses from the pressurizer at or below normal operating pressure with no allowance for continuous spray. With continuous spray, loss of, subcooling would occur between five and six"hours. Heater input at any time of 150 Kw as specified above would more than offset the heat loss and allow system pressure to be stabilized at any desired value. Ability to supply emergency power to the heaters within four hours will prevent loss of subcooling in the primary following a loss of offsite power.
All of the equipment associated with pressurizer heater power supply described in this response will be seismically qualified for the Hosgri event except for those devices specifically noted as non-safety grade Circuit breakers 52-1G-72 and 52-1H-74 will be added to 480 volt ESF buses 1G and 1H, respectively (see Figure 2.1.1-1). These breakers will be seismically qualified and installed to meet safety-grade requirements.
The seismic qualification is based on PG&E's vast testing experience which has previously demonstrated that electromechanical equipment can withstand numerous seismic tests simulating high seismic events without i
damage and that the equipment will be available to perform its safety function when called upon after the seismic event.
Revision 2 III-B-5 3/31/80
e I 3 ON 5ITE EI4ERCIENCY POWER 5Y5TEN ON SITE EHERGENCY POWER 5Y5TEIUI 5AKTY 6RAPE z 5AWY 6RAPE 4.ICiKV BU5 H 4,!&KV BU522 4) 4.u xv/48oV 4V XV/480V looo XVA 4tt>ZZU>H l 48OVSWGR BU5&ECT.l31 2900AHB (SPSP) 480V SWGR. BU5 5ECT.IBE 2500AHP (~5P E) ~ 480V BU&6IOOOIOA OTHER ESF I
a 4~
r I OTHER LOAP5 e) I ~C) ~ d) ~ 0) z>UI) ~ >t) 66I
- 4) IIZ4) E5P I -.4 I ~
4 LOAP5 IPPO OTHER E5F LOAP& IOTHER EBF LOAP5 (izool IM0 I
1 EI4ER6ENCY I EI4ERGENCY PIE,5EL NEW I NEW CrENERATOP I MANUAL EQUIPMENT EQUIPNENT4I I4ANUAL IGENERATOR TI2AN SFER SWITCH TRAN5FER 5WITCH w W W I
Ilt R I.OC.PN5CIHU I WI HCB HEATEII PI5TR. HEATER PISTL HCB L PNL.LOC PS PHIL PNL(OC. PNPHI4.
I 3<<2/p grJzp phlr.l It ~tl 3<<do 3k Ntt>H4 .1 gr Ithll4.tl 0
>ZUZ K I I .I I I I I I 3<<yt 3<<tlII lrtt %hill 4I3<<t/0 3<<2/0 3<<% +43 hr4 4 I 3vt/0 0 KH KUZ K>Z I I I I I I I I
CONTAINHENT NPrlll.pl3<<I 3' 3<<2/0 ~
g 62hZ ZI I IF44z>> 3<<l/0
- LECTRICAL UZ OZ I
I PENETRATION I I I I Q'P>CAL) IMhzlt7 2 >I>h44'2 thr4 bl I SPARE I 5PARE 4 I 5PARE p4 SPAR F p
HEATER PISTIL their'C 6ROuP IL 4I4KW 6ROUPI4 414 KW HEATER PNL.LoC. ePHI2 O PNI. LOC. PNPHI3 3VI 0 fttKIH rthat+23rl/0 CONTROL BACK.UP ~MIHI"IMts3tl3rl 3'2/0 Srt 3v t0 O 0 I I I I I I I I KUZ 3 2lI3 3VI 0 I
I
~i IZZ'3 rthzzHI g<<I/O I
3"2/0 KUZ 3v 0 3S 0 I52t<<5'3 08-"'I5TR.I3SI 0 I I 3T2JO r2(0 3rl/0 5 h<<2 v Ithzlt 4I 34I/O I NIH 35 3"2o 3V 0 I I I I I I I I 3<< 0 I32hlzt.t Ittlllt+ rthr38 I 4~ SPARE
'rOO 3" 4 I SPARE 6~LOUP>Z L KW 6ROuP l3 BACK UP 483K'ACK.UP Revision 2 CM BILL OF MATL 3/31/80 PRESSURIZER HEATERcl OWQ UST SINGLE LINE PIA6RAN SUPSDS FIG.211- SUPSO BY
- B - ltI 1'll SHEEf NO.
PESC<<ll>hpII OMJSVEC PACIFIC GAS AND ELECTRIC COMPANY IIEVISIONS SAN FRANCISCO> CALIFORNIA y INCH
Section 2. l. 7.a (Continued) provide automatic starting sequences after bus transfer either with or without safety injection. Each pump is started by a separate relay or timer from redundant SSPS trains A and B. The motor-driven pumps are also automatically started by trip of both main feedwater pumps.
The turbine driven auxiliary feedwater pump is started by opening steam supply valve FCV-95. As shown on FSAR Figure 7 '-18, this valve is opened by SSPS output relay K632 or K634. Relay K632 initiates for starting on loss of offsite power and relay K634 initiates starting on low-low level in any steam generator. Loss of offsite power is determined by low voltage on the 12kV reactor coolant pump buses. An automatic starting signal is provided by redundant SSPS trains A and B.
The system valves are normally open and require no actions for system operation..
The auxiliary feedwater initiation circuitry is part of the Engineered Safety Features (ESF) system, and as such, is installed in accordance with IEEE Standard 279. This standard is referenced in 10 CFR 50.55a(h) ~
The auxiliary feedwater initiation signals and circuitry are testable. Such testability is included in the surveillance test procedures for the plant as delineated in the Plant Technical Specifications.
Revision 2 III-L-4 3/31/80
Section 2. 2. l.a (Continued)
PG&E Res onse and Status Prior to OL and at annual intervals thereafter, the Vice President Nuclear Power Generation will issue a management directive that emphasizes the primary management responsibility of the Shift Foreman for safe operation of the plant under all conditions on his shift and that clearly establishes his command duties as defined by the Administrative Procedures described below.
Administrative Procedures are established which define the responsibilities and authorities of the Shift Foreman, and establish lines of succession.
However, these procedures will be revised to more explicitly address the Task Force concerns, particularly those dealing with retaining breadth of perspective of operational conditions affecting safety and remaining in the control room under accident conditions to direct control room operational activities. These new provisions, as are all applicable administrative requirements, will be incorporated into the training program for the Shift Foreman.
A list of administrative duties of the Shift Foreman has been provided to the Vice President Nuclear Power Generation, for his review and action.
A review of the administrative procedures defining the Shift Foreman's (shift supervisor) responsiblities is under way. The review includes the subject of chain of command in the event of temporary absence of the Shift Foreman.
Revision 2 III-V-4 3/31/80
Section 2.2.2.b (Continued)
PGGE Res onse and Status The permanent onsite technical support center will be located in the Turbine Building buttresses. The design criteria has been formulated. Detailed design is being issued with construction and installation of equipment to be completed by January 1, 1981 as shown on the schedule in Figure 2. 2. 2.b-l- A complete description of the permanent onsite technical support center is presented below. A discussion of the temporary onsite technical support center follows the discussion of the permanent center. The schedule for the completion of the temporary TSC is shown in Figure 2.2.2.b-2.
PERMANENT TECHNICAL SUPPORT CENTER:
The permanent onsite technical support center (TSC) (common to both units) is located on the upper level of the Unit 2 end of the buttresses on the west side of the turbine building.
V The floor of the TSC is at elevation +104.
Access to the control room is via the east door of the TSC, across the Unit 2 turbine building at elevation +104, and then to the control room at elevation
+140 via the elevator or stairway on the east side of the turbine building.
It takes approximately three minutes at normal walking speed to go from the XSC, via the stairway, to the contr'ol room.
- 1. Emergency Function:
The principal function of the permanent onsite technical support center (TSC)
(once activated) is to serve as the headquarters of the Site Emergency Coordinator, Liaison Coordinator, Evaluations Coordinator and their Revision 2 III-Z-10 3/31/80
Section 2. 2.2.b (Continued) staffs throughout an emergency. Provisions have also been made for the establishment of an onsite NRC emergency headquarters in the TSC. The TSC is sized to accommodate a minimum of 20 Company personnel and five NRC personnel.
The floor plan of the TSC is shown on Figure 2. 2.2.b-3.
It is planned that following activation of the TSC, the overall onsite hssessment and recovery programs will be directed from this location. In addition, most communications with offsite locations will be handled through the TSC.
One section of the TSC has been outfitted to serve as a radiological counting room. This facility is intended to be a backup location for this type of work in the event that the normal counting room is unuseable due to high background radiation levels.
- 2. Habitability Objectives:
The TSC is designed to be habitable throughout the course of a design basis accident. In accordance with NUREG-0578, as clarified on November 9, 1979, the TSC shielding was designed to limit all direct radiation exposure to 10 mRem/hr assuming TID 14844 source terms (from Section 2.1.6.b studies),and to limit all airborne particulate and gaseous exposures (internal to the TSC) to 5 mRem/hr. The total exposure to any individual in the TSC would be limited to less than 15 mRem/hr from a time period beginning one hour after the start of the accident to 30 days later. Over the quarter (3 months)
Revision 2 III-Z-11 3/31/80
Section 2 '.2.b (Continued) beginning at the start of the'accident this design will assure that personnel inside the TSC, will not receive quarterly doses in excess of those specified in GDC 19 and SRP 6.4.
The TSC is provided with its own ventilation system, shown schematically in Figure 2.2.2.b-4. Both redundant Class I pressurization fans provide the TSC and related HVAC room at a minimum pressure of approximately 1/8" water gage.
Both pressurization air and return air (1000 CFM total) are passed through HEPA and charcoal filters. The pressurization air exfiltrates from the TSC to t the outside atmosphere.
from a normal power source.
are designed to Seismic Class A self contained air conditioning unit is provided for the TSC. The air conditioner is not seismically qualified and is powered The duct work, I criteria.
ventilation fans and filter units The laboratory is provided with its own ventilation system, shown schematically in Figure 2.2.2.b-4. One fan provides ventilation air for the lab hood and provides enough pressurization air to maintain the lab and related HVAC room at a minimum pressure of approximately 1/8" water gage.
Both lab hood air and pressurization air are passed through HEPA and charcoal filters. The pressurization air exfiltrates from the laboratory to the outside atmosphere. The exhaust air from the hood passes through HEPA and charcoal filters before being discharged to the atmosphere. A self contained Revision 2 III-Z-12 3/31/80
Section 2.2.2.b (Continued) air conditioning unit is provided for the laboratory. The air conditioner is not seismically qualified and is fed from a normal power source. The duct work, ventilation fans and filter units are designed to Seismic Class I criteria.
The normal lighting for the TSC is provided from the emergency AC lighting transformers. Backup DC lights are also provided.
- 3. Special Equipment:
Provisions are included to permit persons in the TSC to monitor important plant parameters. The output from each Unit's P-250 computer is sent to the TSC using a hard-wired interface to a Harris time-share terminal in the administration building, then to the TSC via acoustic coupler. Figure 2.2.2.b-5 shows the flow of information (plant parameters and health physics data) between the plant process computer, health physics computer, TSC computer and various peripheral equipment. The figure exhibits the capa-bility of the TSC computer to provide all the necessary plant and health physics data to offsite facilities. To provide backup for the plant computer, closed circuit TV cameras are located in the control room in a such a manner that the console, main vertical boards, and the post-accident monitoring panel can be scanned from the TSC.
Revision 2 III-Z-13 3/31/80
Section 2.2.2.b (Continued)
The TSC is tied into the emergency radiological monitoring network such that one compartment in the TSC is set aside for analytical work. The principal purpose of this facility is to provide minimum onsite analytical capability in the event that the normal facilities in and around access control are unavailable. Multichannel analysis capability similiar to that in the counting room is provided. A thermoluminescent dosimeter reader is also provided. Two radiological emergency kits are stored in the TSC. Contents of these kits are indicated in Table 2.2.2.b-l. Finally, the TSC is provided with a terminal and printer for the Company's computerized records management system. This provides the ability to inspect and print the latest copies of all prints and records involving the plant. Also current hard copies of the most frequently referenced drawings are maintained in the TSC.
- 4. Communications:
The focal point of communications for the Technical Support Center will be a central communications console located in the computation area. The permanent onsite technical support center (TSC) has been designated 25 CBX lines.'his console will house three communication facilities. The first facility, a CBX telephone control center, is called a turret. From this location, all incoming calls can be answered and/or transferred to designated personnel for response. The turret can also be used to obtain an outgoing trunk line for use by the TSC, even if all should be busy, by intercepting the busy line and asking the parties to discontinue their conversation. This turret will normally be shut off except during an emergency. Normal day-to-day operations Revision 2 III-Z-14 3/31/80
Section 2.2.2.b (Continued) will be handled via a similar turret in the plant administration building.
The second facility, a telephone answering station, will house those telephone circuits not accessible via the CBX. As shown in Figure 2.2.2.b-6 these circuits are labeled with a "B," "E," or "G" symbol. A "B" symbol represents an extension from the exchange at the PGandE San Luis Obispo exchange. This circuit will provide direct dial communications into PGandE's Los Padres 1
District Service Area, without the need to use one of the eight trunks of the Private Dial System. The "E" circuit automatically rings the party shown upon lifting the handset and depressing the button of the location desired to be called. There will be one button for each dedicated line to the control room, NRC Headquarters, and the Offiste Recovery Center. The "G" symbolizes a standard unlisted telephone from the Pacific Telephone Network. This telephone will provide direct access to an offsite location in the event the Company exchange system is not available. The third facility is for control qf the power plant's VHF and UHF radio systems.
TEMPORARY TECHNICAL SUPPORT CENTER:
The administration building located west of the Turbine Building has been designated as a temporary onsite technical support center. This facility, with the addition or extension of some telephone circuits, portable radiation Monitors, and the provision of a portable closed circuit television camera, Vill be functional from June 1, 1980 until the permanent TSC is completed no l'ater than January 1, 1981. Figure 2. 2. 2.b-7 is a diagram of the layout of the temporary TSC.
Revision 2 III-Z-15 3/31/80
Section 2. 2 2.b (Continued)
The administration building presently contains a Records Management System terminal providing access to plant design documents and a time share terminal capable of providing output of important plant parameters from each Unit's P-250 computer.
Portable area type radiation monitors with a range of 0.1 to 1,000 millirems per hour with alarms (Model GA-2TO by Nuclear Measurements Corp. ) are available onsite. One of these monitors will be placed in the temporary technical support center. Airborne radioactivity concentrations will be monitored with a CAM (constant air monitor) which will be made available for placement in the temporary technical support center.
The closed circuit television system equipment to be located in the permanent technical support center is expected to be onsite by June 1, 1980. It is intented to install the cameras in the control room and to initially install the monitors in the temporary technical support center. However, should delivery be delayed and to provide backup capability a portable television camera would be procured for the temporary technical support center. This camera would be utilized by a camera man in communication with the temporary TSC to scan the control room as requested to provide specific plant parametric information.
Revision 2 III-Z-16 3/31/80
Section 2.2. 2.b (Continued)
Telephone communication circuits currently exist between the administration building and the control room, the'Corporate Incident Response Center in San Francisco, the NRC site office, and the NRC Operations Center in Bethesda.
Additional telephone circuit modifications will be made to provide dedicated communications between the temporary TSC and the offsite Emergency Response Center in San Luis Obispo near-site Emergency Operations Center, Control Room, and NRC Operations Center by June 1, 1980.
Revision 2 III-Z-17 3/31/80
TABLE 2.2.2.b-l CONTENTS OF RADIOLOGICAL EHERGENCY KITS UANTITY ITEM Instruction Binder
'a 0 Assorted Pens
- b. San Luis Obispo County Map C. Equipment Location Dwgs. (sets)
- d. Emergency 100 100 100 100 100 Environmental Mon-
.itoring Field Data Sheet (Form 18-9259)
- e. Appropriate Environmental Monitoring Procedures from Emergency Procedure R-2 (sets)
- f. "Emergency Kits" (G.A.G to Emergency Procedures)
- g. Corporation Key (3A90909)
- h. Pocket Calculator
- 2. Monitoring Equipment
- a. Dose Rate Heter 0 0
- b. Dose Rate Meter 1 1 C. Survey Meter 1 1
- d. Standard G-M Probe 1 1
- e. Pancake G-H Probe 1 1
- f. Pocket Dosimeters 3 3
- g. Dosimeter Charger 1 1
- 3. Air Sampling Equipment
- a. 12V Air Sampler .0 0
- b. 12V Air Sampler 1 1 (w/battery)
- c. 120V AC Air Sampler 0 1 1 0 0 d..Air Sample 10 10 10 10 10 Particulate Filters (pkg.)
- e. Iodine Filter
'Cartridges (pkg.)
III-Z-18 Revision 2 3/31/80
1 TABLE 2.2.2.b-l (Continued)
CONTENTS OF RADIOLOGICAL EMERGENCY KITS UANTITY ITEM
- f. Paper Envelopes for 100 100 100 100 100 Samples
- g. Plastic Envelopes for Iodine Cartridges (pkg. of 30)
- h. Forceps
- l. Compressed Air Cylinder Sample Head J
fit
~
w/adapter to Air Cylinder
- k. Air Cylinder Regulator
- 4. Protective Clothing/Decontamination
- a. Protective Clothing Sets
- b. Full Face Mask C. Type H Ultra Filters for Face Masks
- d. Skin Decontamination Soap
- e. Brush
- f. Paper Towels (pkg)
- g. Smear Pads (pkg of 10)
- h. Plastic Bags 3.
- l. Bucket (10 quart) 0
- 3. Decontamination 1 Agent
- 5. Signs/Barriers a~ Radiation Signs
- b. Radiation Barricade Tape
- 6. Sampling Equipment a@ Sample Bottles 2 6 2 4
- b. Plastic Bags 15 15 15 15 15 C. Trowel 1 1 1 1 1
- d. Gummed Labels (pkg) 1 1 1 1 1 Revision 2 III-Z-19 3/3l/80
2.2.2.b-l (Continued)
CONTENTS OF RADIOLOGICAL EMERGENCY KITS UANTITY ITEM
- 7. Miscellaneous Equipment
- a. First Aid Kit ,1 1
- b. Screwdriver 1 1
- c. Crescent Mrench (8") 1 1
- d. Scissors 1 1
- e. Stopwatch 1 1
- f. Roll of Dimes 1 1
- g. Masking Tape 2 2'
- h. Flashlights 1 w/Batteries
- i. Extra Batteries
- j. Battery Powered Lantern
- k. Bolt Cutter XXI-Z-20 Revision 2 3/31/80
6 7 10 RELEASED FOR APC<lTECTURAL) g.20-80 MECHANICAL 8'LBCTRICAI 8-29-80 CONST RUCT10N ClvlL OESiGU 8 lT.y) CIVIL CO14&TRUCTION ARC'4ITECTURAL COMSTRUCTlOhl I lo.lS-80
(
I I lo-@40 I MEClIANlCAL I AMO ELECTRlCAL INSTRUCTION PRE OPERATIOIIAL TESTS I I I I AND TRAINING I I 5+80 I I I I I I I
MECIIANlCALI OESISN I I I I I I I I I I I I I
I I I
I I EI.ECTRI CAL I DESlGN I I I I I I I I I I I I I I I I
I I I
I I
I 8r. C l DESIGN I
I I
I I
I I I I I I I I I I
-o 6 I MATERlAL ANb E@UlPMENT PRGCUREMENT 7-1-80 9-l-80 I I I I R-80 I I COMlNUhllCATIOkIS l OE5lGN COMMUNLCATIONS INSTALLAT'lol4 los 80 I
I I 5'- I-So 2-22-80 EQUIPMENT PROCUREMKNT Revision 2 3/31/80 Figure 2.2.2.b-l MICROFlLM BILL OF MATL TECHkllCAL 5UPPORT CENTER OWQ LlST SU 1-I-Sl RFQUIRE MERITS SUPSOS SUPSO BT CHKO.
O.K.
SUMMARY
SCHEDULE SHEET NO. I Or I SHEETS DATE PACIFIC GAS AND ELECTRIC COMPANY SAM-l2-OOI p REVISIONS SAN FRANCISCO, CALfFORNIA
~ l~ IXV I 7ll teal%&~% IN&OILWeeWWE~ ~ A I
III-Z-21 4 S ~ INCH
6-l 7-1 COMMUNICATIONS DESICMs PROCUREMENT'MSTALLATIOM Sr TEST I TRAINILIG I
I I
Co-I CCTV DESIGIJ~ PROCUREMEMT> IMST<LLATIOkl & TEST I I
I 3-II PROCURE I puT IN PLAcE, EMERGEMGY EQUIPIAEMT, FURMITURE & FIXTURES I
3-2S I ESTABLISII SPECIFIC, CRITERIA INSTALL RADIATION MONITORS I
I 5-1 VERIFICATIOM OF EXISTING PLAMT PROCESS COMPUTER PRINTER & RECORDS MANAGEMENT SYSTEM TERMINAL OPERATION I I
I
-6 DEVELOP ADMINISTRATIVE AlID OPERATWG PROCEDURES POR TIIE TSC ~ EVACUATION TO TIIE CONTROL ROOM & TSC FUNCTIOMS FIZOM TH'E CONTROL ROOM Revision 2 3/31/80 Figure 2.2.2.b-2 MICROFILM GM BILL OF MATL SUPV TECHW ICAL SUPPORT CENTER DWQ UST DSGM SUPSDS (meZRARX)
SUPSD BY CHKD.
0 K. SCHEDULE SHEET NIL I OF l SIIEEIS SUMPTUARY DESCRIPT%M DAT I PACIFIC GAS AND ELECTRIC COMPANY SW-l'3-OOI O' REVISIONS SAN FRANCISCO, CAUFORN A
~ INN'AT IIÃ) IOOITISOIISEPIM ItH ~ CLEIWNIITINC OH ~ M III-Z-22
0 2O 22 rS P 3H ~iO CO L 33K~M 0
TT
~LIT] 44C N
lc 8~2 AN QTL H N BS Q t4 L2U 0-6C, Q
IP IP IA 4 TJ Q OPPICS QE orenrnxrua cttvrea Qa CCACPUTATIOM COHTOR MRO OPPICg NVAO ROCAA LASORATOR'V QS Pa QO KI ttdtA
- OTV. CC CCRt PTION ,ITCCA CETY. CCCCRIPTIOH ffCIA Cfrc DOOCRIPTECM IYOA CZ1Y.. CldOCRIPTIOM
'A
~Cot(OO AAANACISCTTENT CPTSTEEIAO)
O EX!CH(CCEOLO t(OCEICLW LCEX) I cc'Tv'ADHfroR I OEWACIHtctcftCEta CCEURACHT I CRT'ORCNHAL OA 2 DCCIC (DCESLC Pt(SCttLWLOOC) 2 NVAC UNIT~ 7A I tt I TASLS (O'iXLLOt) 2Q I p Oco ttcAIDTs ccNITCLrp I 4a IC YAOLS (Sect X SLCP) i CRT TdtffEPCAL CS 2 TASLS (2LOIXC'-Ot> OS g, Ag, RgT(cALRT4 7S I LOAO CKCLOOM OCEPCTSR IO I
I OLtttANCP PILS 20 I
I P AOCC554R CCNTICCL CONCCEC 2$ 0 DATA AIONITOR I
I LINC PlbHTCR COLOR CEIUPHIC TCIUAPCAI 4C 4O I
I IMT IEO RSAOIIRIPltNTllR A(tCO atLg SO 2 2
CHAIR (CWIVCE )
CHAR (OUCCT) j'gc)8'. 4rAOS 7C I TITRRTOR 7O IS I C DRAWCR PLS AfLOOK 22 I OPIA CITS DATA IAONITCR 'TCO TORY MAL 42 I OCS TRI LONC t%AOCPt SS 2 C CRAWSR PILS Wl LOCK N6l4l~RS 72 I
I i
OINK (DCACPCCRALI2SO)
IP O SIDS LCKO PILS Op a PRINTCR 2 CPCH(CCIUOLO ~mW L44IC) ar I I TSL.SPICONtt COUPLSR l44lic)ki()n i AR(.g A()l)n'o~
COUNTSR W APOINEEES OVSR IP CHAIR (CWIVSL) 2CP I CICC Ottlvg OO I TAOLO (CLCtX4LOI) 40 I CAROLtOSL IK CICAIR (CUOCT) CH I TAPS ORIVO I 'TAOLC (OLOtX IELO') 4H I OCCK (DOICLC PCECCEILWICGC)
Monitor 7'I 5
II RAOCATOH AICPHCTOR aI I RCAOCR SZ I ADUUOTAOLO CHCE VIIAO 4I I TASLS (2LOIXCLOt) 2 VWSII EC&C(2LIELCP¹24TCLWEEEOC)
IJ TCLCPICOIIO CAOtttt CAEIIHCf SJ I PROC 2 CCOR SJ I Cctd LOAD PILS 4J 2. CHAIR (CWIVSl ) 7J TLO IgACOR 2K I PR INTEER QK 7 CHAR (OWIVOL) 4K I I ICHTINC TRANCE)PffACR 7K 2 TAOLO (244 X CECP) 2L I l4hOCATIOt4 ACONITC&t Sl 4 CWuR ( OUOCT) 4i I 4OOV. Ac PAMSL I CAIAIAADdfdcftctt CKSLO 2IA 2N I
I CACOOTTlà DOCK Pl.CITTC R SIA 3N I ttAECIOEECICtttftxttCNTR IETOL 4th I CCEICIECIHICATICIH CAONLT 4H I l2OVC AC I lOHEIHOPANCL. 7AC I, AICA I INOTRUIASNYAC PAMSI 'TN I . CEcAPUTSR C OICC 2O 2 1AOCJI ( 2LOixCLCX) ( RgrROOUCTIOM) '74) I 'CCOROONCY CHOWCR 2P 2 40 I XCROX lAACHIN d 'TP I STTE VIIAOt4 20 I CHCC VPCC RCR CRVEC RNTTO 4P.. 2 (PfHOCLVNEWAEECEEHE'JOTCEEI TO I Pl ltd ILANKST 2lt 22 2T I
I I
~lot C~CCVWCE PDR OUPPLlCC UCTtffLRES 11ON CAS'NOT Rtt TAPS CiDRAA 4 4t
+EL I
I T¹CPHdtcd 4AOLttit 4AOtHCT 4CINANIAATUH CAEEIHif TR 72 I
2 Pve( COUHTSR CKhR (CWIVSL)
TT STOOL 2U I Ptlftlttd EATA UIAC 2EIIVCNr I TE 72$ TZIACINAL 2V 2 DATA PCCSCO fatfftENAL 7V I CLCCTR& VIATSR HSCITSR 2W 4 CHAut (CWIVOL) ccx>o cco 7AE I '¹t('EEOECS 4AOLIILT 4Atcttdf I Radiation Plow i%or
~ tlf CIIPP4ttf CCIIEOR I C 4 4 ~ ICE FLOOR PLAN CCAl $ IM PCCIT TECHNICS GVPFDRT CENTER NNRcH l9, lR80 lzav. Ho f figure 2.2.2.b-.3 Revision 2 III-Z-23 3/31/80
0 Mdftt5 OP OPttATIOFC IN TCCIIFIICAL 50PPITT CCIITCL CIM'hf htttf hSSIS CCCHCVIATCO AH dftHATIIH VITH 4$ %dltf&OCAK TO MAtc I'f Vota AJA TIICO I@4'HIH4 I ILTCHIfte Use OUKIH4 HOCIIAL OfelCATIIVS a p 0 II HOT AftlIOAOLC III SS CICICCULATVH AC dfCCATVH VFITH 1% Ace THOU HCPA MECHAIIICAL COOM Ate OHACOAL fhf east fta Ust IH Tcc eftcf Of HICH Atattttc Chth Ott II I O C lOOO CHI-ha CAOPAOFIVHY OS HtOH CHLPHIHS ~CWTCATIOHS 7 OPTH IOCCH fi SOUTH POfsOC AIH I ttsscclaATVH IHLefCI I
ct he OS hh I IA IP,SIP Oh CCOKOAATCO A1 PtchttVH VITH fte CIMSIHATVtt KN I I IS I dt SII 0th fatS~CATVH AIC AHO SFPCfh tt PPOCOAATVH OH VITAI. SCS VCVFCM VPO SfAHO Of LOOP OM AIh tta + fP~M It VIICth THCFV4ta HCfA AHO CAHOIH fafttsl tte Ose Pt THC cvCHT tt Ahotctd ctovAcflvtfv. Hthft AHo fLftant I 0 0'0 h-Icdd ~
0/A NOC77I CHIF OP OLCF 0 O.CS HICFIALLT 0
Otth Ct SP S
Htfci sPllll facsscefAftH TIIAPIS of HIT ottcPcc shUIIAHctttsLT t/c fACACLCL C/ltfatL
'1 C ~ OC+ ~ IH$7 ttth tvttS df dfttATVH OPC4 C tl OS hS O1 hh I I~
HCOUHOAHT C CAP IAII IIS ~ hS IwC I'AH tH VlfikLOCS TCCHNICAL 5UPPOCT Cttlfet, altd cph IS SIP Cttf
, e S SILT CATV 4 OFCIS OSO-S tl I 1 II I I I0 hk OFCV Cti tt ts I 0 0 h HF> IH VITAL OIIS S 7'OP VOICth VIS STAHO Of h >AFO 5OL' tiV OP .LKChht bl04. I >7 S.O l4 IO.OAF 0 M h ICPO C Itd OOO h Std ctL AC
>d otc ca ts ~ SIt IH VITAL OCS ds ~ G Cltd CPM th II I .e IF 4tt P lt CICT OIL CAFH IBGjttIO VENTILATION SCHEMATIC- TECHNICAL SUPPORT CENTER TVO ftslflhl CLCCTKIC MOTIC Ctl I.
I CCAftO OAftfte COOL PCS I/A,.
G AÃdOC AIL PITAHC QQ PAII OS hl ttll'ah fO.hd g edl4IIH4 PLT va H 6ALAHVH4 ~tc 0 Cth HOCIIAL IPIP CPM ACCIOCHT h
a ht CP At I I I Q HafAPILTCP. ~ PLCX,CLC CIH~CTVH CLIPCO ofek Hdeht I.
I c&oeHT g 0 ACCOAL thfte ~ dActa OCAff oAhrec JOCS l'rf tfatATdtt Alt.
IICCIIASICAL tCIIIPMCIIT Ctdtf OS Oh PHS CIP Cth Vdttlt L CHP't TVFtl 6 ~AHllAL HAHO sttfCH h ttt VOL PI Cfh CIOCfh HPCHAI, 0 Oh ACVOCHf 8 C~ ICIHC Ocfecftk 6 oetelaeHTIJ4 Ptcsscae svlfcH CIISCO ACCCFCHT otev htahkl.+
PAaf Cl(SCO ACCOST ~ASPERA Pc. fltd OM ACC Xh 8 CAOIATIIH CCTCCTOC SMOHC Oef Ccfdla 0 c H CATIH4 COIL I CIIHotcAfcs eatcfcd A Poslflve shcf dtt MP HUP L OAMPCIL
~
Oe hh I4000thOM HPCMAL FO'hh ACIJdtttf HFPO Figure 2.2.2.b-4 Revision 2 VENTILP TION 5CHEMATcC.LAEOQTOK'f SUPPORT CENT% III-Z-24 3/3X/SO
Ill PLANT PARAMETERS A k klan PIC PIC PIC ALARM I/O LOGGER RMS LAB D TA M MX DATA PIC PIC PROCESS MSD H/P MX COMPUTER COMPUTER PIC PIC PIC I
I MET DATA I CONTROL I CONSOLE I
I REMOTE CONTROL DISK TAPE CONSOLE CONSOLE P/C DATA 0/SDATA MONITOR MONITOR CARD PRINTER READER 0/SDATA PRINTER PLOTTER CASSETTE I/A I/A TERM TERM M M M M M M M IBtE OEB OEC BCS N/A NSSS ISC Figure 2.2.2.b-5 Revision 2 III-Z-25 3/31/80
PENCE PCj)E OFF- SITE SAN LUI5 HRC OBISPO KDQTR5 RECOVERY'ENTER DIAL 8ETHESDA S4N LuiS OBISPO EXCHANGE AthRYCAHD DIABLO CAN'7'OP/
POPVER PLANT rowER, PIVSITE PACIFIC I'LANT Ci) LiNE TEC E'PHOHE TECHHICA L 0/A L CONTROL SUPPORT ROOM CENTER TELEPHONE SYSTEM DIABLO 0 u.
CANYON t 0 DEPT OF PWg. PLT. Al ENGR. 4U HEALTH RESEARCH PHYSICS g4 qO SAN RAMON OFC, E OF'FS/
LA8 CALIF.
PLAN 7 CB 75) LINES POWFR, (a) LINE5 QB POLYTECHNIC PLANT TFCEPHONES EXCHANgE 4r~
HUMSOLDT SAY rowER C PCANT n
OPERATIDNhL reCE C ORP ORATE suppoRT RESPONSE CENTER CENTER SAN FRANC ISCO C EGEHD (SECURITY BLDGJ QA DFDIC47FD DI5PATCH TIE LIHE5 QB OFF PREMISE EXTEhlSIOH MOB IC E riE TRUSS LABORATORY QD CENTRAL Opf/Cf TRUNKS (Zo DIDi Eo DOD)
QE DEDICATED TIE LINE QF PCF $ 8 PRIVATE EXCHANGE C IHES I
Qg rh cIFIc TEL EpHoNE ATC- ATTEHDhHTS CONSOLE ExcHANcjE LINE P I'5 Ljgg 2.2.2.b-6 TECHN/ C A L S OPPOSE T C Eke@
re gE PRI VATE DIAL TELEPHONE
$ 7$ TEM TE'LEPHONE COhfML/NICATION 5VS78hf Revision 2 III-Z-26 3/31/80
UNITS 4 LFTO>> ri CO'-Or SL" E Slr. R LSI 'll IIOl% 19th ADEOITA0II SEC PWSN N'59TI'5 E4.' "44')
il fO'-aa f<a 5'4arC'SOCILAR TCa Eels 59 II5r LC Oa S'4S re .ter e"s: I s's reps P'Ij r.s r
r.a' lrH5 'seOT S'e s41 I
i I
) 1 I'I I
I
(rP AwI 1
alEK u 1 I ST MC el CPPca 0PFCt5 m t> Itr ~ eS TS IsCGO IIRSISARJatlON S S5ScarTGe.@
TJOMKX b
L,.!Qj sssssasae Q SEE. JISM. +
AIlrCR Slee 4'P&raNSWQS0415 laisser p4T s' 597 RO j@ la TS re 1
QI5' Ic ~
E.SCT
)
1 WATSIS COCABA SSIIISRS
'BI
~ ISCI'ccAAR I
iasLIIIocoRB j EMILY HCret-OSOICATOSO aIAOases YrPrei PHPHB55 IarPTtITCIR "I STO I ~ 55 TSLBarsIG Ittssc
~
C~II
~
TLALETIQ E)CI SN I SJPUNIIOR.
CRA55INcNC f RILE s I
OFFIC SOARD Lnl i
. TRhuIIN4 LtIXcK PLCCM
'TSSArYeBsirtANaC eF Vi'OL ga i g LOSST FT ~~Cssasss N TECHNrcsAL C'dFI5SSST C ESITttSS b g ceCCCTCsesTSO HsSist O
Dr Qa.
SKCURLTT OFFS ceorCrCIBO ITS'h IICSIBNSE CENTER
~Y SsNCTaO TB I AAOet 4TOE0ICsATOCS OEOICeAYECr ETSIS5aCI4/iTIAItILsertO
,CT DEPICT NEAR-SITL EAeERCCNCF CSTI/EATCSIS CSNTCFL ~ SARTY LATISa NTS 9 COUXllRTIITII i 0' OTHER POArESS ec ~ Ii SKLIITfay ! VI MRC
~O) r QO QO ,ei I i'jr O'
IAJ CFFicc
+ I s FRCs 'TFLAsILSR ij!
- I I I II'
); )I 1 e IIra I !
1
, 1 rcccp i I ~
) I i
- I'.
- I II il ri 1
(TYP.J I l I
le iii 1 I l)l l.i 1
-,! I Cy4a
~ ~ 1 rNP NCF ~5+ Qf+ rII'rrArre'~s. 'reer~lair~ass re 1 SsNr ! 54 I
Ss4 1 r4 I54 f4 CALLED NORTH 80LS
~ST I&
IO CLOGS OUTLET IR5Y CLJPLSX RECBPTACLm I& Figure 2.2.2.3-7 Kl OPRCJIL POJJIPL CUTLET FOR KQUSTMRNT pEI=ERENCE DIJ'G. Revision 2 ITC155 IOIMB,~IIyOOSR ICR LCC4TCN CF I4 R4.,lS. TILLal%0IaTs OUTL 5'T BOX JILT- IT. TILLILPIOKI5 OUTLILT @Oh IIl-Z-27 3/31/80 NUILTOIU3 CX TNR QITTI.
I5IIT~ 'L2 IOSI SSITI5 SICBS CN NNITIIINII ~ saA>> rereesw carr er ~ . TNas rre TEICKK)5RT ggPg$ TRATIIN 8JLOINC See raaas MST II ~AC'V 1
Itr ASeO. Wbd I)EIJUIREMENTS wrceeerscs It I TI AS drrLT ces' cs rse. L 595O9 I IS I ASIIApsrCP t I.ISti T reW Csa.
are a
e'T DgeLO CJJITON weceeersco sT OI ISSIICP teSC VS SIFC.IS oere 5 ~ SIS555ISO NeecT asar. I s I I eaaecr OATS sar ~T csa eeo PACIFIC GAS ANO ELECTRIC COMPANY TABLE OF CHANGES TABLE OF CHANGES 55 ~ OIKO SAN rsNANCISCO. CAIISOSNIA
I
/
HPHPI-lHSr SulL DlHOp f
l C OH'TAlHylgH >>HtW I g,ddt&
AllyI Ijgz'fL I 8$ $ t4C pike.g, , &LCbr. urge i $ g r vr I
Pr >rz7R +r i7I yl pll r,>rr rrr rrr rid t4 I"rr rrrr rrrrr I
.c-'rrr
+j'rrr r rill2&cdJ/ I luaulan'uSL I
STplae $ ~ ~ ~ ~ ~ ~ ~ ~
I 8 f- W4'6'l>H I fop g 1HS sl..86 q~ sL-.I&o' I
RQil PlHGr 014 I 8'0, i g gl Bf'Hf 5L,5fOP. ~-"~. fnsl .t40; .
S,l,. 89'To gl..
>l PW~c Hp L.
YAWP &IJ p'p'PAL;.f TWNHioP w Sl.. Ã ~SHfSW
>4J'Puli; >&Tao (59GURlfY Sui~aiNa)
/
T&Hj nP-P Rf D I &5 HA&+6 APHlNI&7!4ATIPN 5fguc fute&
grill PIH4 GFMRRAl SITE Pl.Akl
, iMPVCH lS,IW80 JZEV. i@2 5 Figure 2.2.2.b-8 Revision 2 III-Z-28 3/31/80
0 Section 2.2. 2.c Onsite 0 erational Su ort Center Task Force Position An area to be designated as the onsite operational support center shall be established. It shall be separate from the control room and shall be the place to which the operations support personnel will report in an emergency situation. Communications with, the control room shall be provided. The emergency plan shall be revised to reflect the existence of the center and to establish the methods and lines of communication and management. (Category A:
Implementation shall be completed prior to OL, or January 1, 1980, whichever is later.)
PGSE Res onse and Status
- 1. Location and
Description:
The security building serves as the onsite Operational Support Center (OSC). The security building is located on the southern perimeter of the Protected Area. The OSC can handle approximately 38 individuals at desks in its nominal 1,600 square feet area. The OSC contains kitchen and lavatory facilities.
- 2. Emergency Function:
The OSC serves as a staging area for support personnel who are called to the site to provide support activities. Use of the OSC eliminates unnecessary congestion in the control room and TSC, and enhances the implementation of personnel accountability measures.
Revision 2 III-AA-1 3/31/80
Section 2. 2. 2.c (Continued)
- 3. Special Equipment:
The OSC, located in the Security Building complex, is provided with PG&E and PT&T telephone facilities as well as radio communications. This center will contain one CBX line as indicated on Figure 2.2.2.C-l. The CBX will be programmed to allow the telephone serving the Operation Support Center to have sole access to critical telecommunication lines.
This feature insures that the Operational Support Center will be able to maintain an open line with the control room. Two "evacuation kits,"
containing portable radiological monitoring equipment, and other equipment useful in an evacuation are stored in the OSC. The contents of these kits are listed in Table 2.2.2.C-1.
Revision 2 III-AA-2 3/31/80
TABLE 2.2.2.c-1 CONTENTS OF EVACUATION KITS QUANTITY ITEM PER KIT
- 1. Survey meter with standard G-M probe I
- 2. Dose rate meter
- 3. Self reading dosimeter pencils, 0-200 mR range
- 4. Dosimeter charger
- 5. Barricade tape, 100 foot rolls
- 6. Packages of 2" filters (10 filters/pkg) 50
- 7. Bul 1 horn
- 8. Plastic bag (14"x24")
- 9. Pens
- 10. Flashlight
- 11. Pocket Calculator
- 12. Corporation key (3A90909)
- 13. Information Center emergency room key
- 14. Instruction book with evacuation procedure and data sheets Revision 2 XiI-AA-3 3/31/80
0 Dlhtld Chard+ trefl/A/f PPNFjf Plhkf Pd O'FR fflFPfdk'f5 Pl/II/f CPN/gdl QPdhl hC/f /C Flfpgtkf Dlhl SFlfrkdkf SPSff +
~gS
)pl 411 P'ld'F PPFghf/dkhl f <If /INF OF //'lhkf
%FR rt/ VNWS C
~/VhfF Dlhl SVPPdg CfkfFR FA'C/VhkPF fSPSf FlfPIIPNF FA/
fSFCVglf/ SullD/Niff P//C F PF/ SITE RFtd VFRT CFNFFR dkSITE Shk /VIS Pris P ff t/lk'/thl SI/i Pdgf CFNfTFIT LFFFND:
Qh DFDIChfFD Dxsf//fthm f/F ll/fs Qb If'//Fhd/sf AffNSIPN f/F fgrNgs QD cfkfghl ll'5/cf fRCN'4$ (N'ID, N DPD)
QF DFDICgfFD f/f le P'g C f PRIVhff A'Crf/NFF llkfs QH ATC- h TTENDhHTS CONSOlE F l'NIJRF 2 2.2.c-l rrfphilpKIL sejrrgf cfkffg JFlFj/pkF ere/crklc/Jerk sysf&g sfc// /f7 PraDIK'd III-AA-g Revision 2 3/31/80
Task I.A.3.1 Pre are A licants for New Exams Position There will be new scopes for the examinations and criteria for the issuance of reactor operator (RO) and senior reactor operator (SRO) based upon Commission Action on SECY 79-330E. There will be a new category on the operator and senior operator examination dealing with thermodynamics and related subjected'ime limits for applicants to complete the examination will be established.
The passing grade will be increased to 80 percent overall with a minimum grade of 70 percent in each category. Senior operators will be required to take oral examinations and the requalification programs will be changed to reflect the new initial requirements for issuance of licenses. The licenses will prepare applicants for new examinations and will develop and implement new examination criteria and lecture schedules for the requalification program.
PG&E Response and Status PG&E will implement the position as required by the NRC. The implementation will be completed before issuance of the operating license.
Revision 2 III-EE-1 3/31/80
Task I.G. 1 Trainin Re uirements Durin Preo erational and Low-Power Testin Position Near-term operating license facilities will be required to develop and implement intensified training exercises during the low power testing programs. Licenses will (1) define training plan prior to loading fuel, and (2) conduct training prior to full-power operation.
PGGE Res onse and Status See attached letter from PG&E to NRR of February 7, 1980.
Revision 2 III-NN-1 3/31/80
I