ML19323F283

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Proposed Tech Spec Changes Including Revised Pages 234f, 234n,234o,243 & 244
ML19323F283
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 05/23/1980
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML19323F261 List:
References
NUDOCS 8005280726
Download: ML19323F283 (5)


Text

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en

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O 4 1-GG-S-3$ l .S h '. 155 See X Lr>well 1

4.11.D.u.b 1-GG-S-3b MS n 's 15S X DIy ell 1-GG-S-63 MShV 155 X DI)well 1-GG-5-64 11S h 'v 155 " X Drywell i 1-GG-S-b5 MShV 155 " X Drywell w

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a 1 uG-S-66 MSnV 155 " X Dr>well 1-GG-S-6 7 MShV 155 " X Drywell 1-GG-S-68 MShV 155 " X Drywell 1-GG-S-69 MShV 155 " X brywell 1-GG-S-72 MShV 155 " X dis well 1-bG-S-74 MShV 155 "

X Drywell 1-uG-S-7 5 MShV 155 "

X LI).eAl

i-GG-S-7o I;ShV 155 " X Lr) ull I

l uG-S-7 7 hSEV 155 "

X o r y .e-11 i

i 1

PbAPE unit .

tat d 3.11.6..

EslSli_utia ea SnocA Scati m old_p auoters1 Si4UcetR li. hIGrt (1) haDinTIut. St.0bb .hS al.v.m..i.S $14Ubbr.n d AREA ESPECIALLY i t.nCC .SSioLL hCCt.SS It:LE S% bora Dun 1NG blFFICULI auiu?.G teOrit1 AL DURIhG h0MMAL N U.< b c.It log AT IOr. LLM6110N SriUTDOWN 10_bEMOVE __tEt. NATION __QEQA_110N __

23Deh-3-26 rIt1 117 See X Torus Mcom 4.11.D.4.0 2 3 -Def.-S -2 4 hPCI 117 " X Torus Room 2 3 -ii ti-S- 3d HPCI 93 "

hec 1 Room 23-nb-S-36 HPLI 103 "

HPCI hoca 2 3 -tib -S- 37 hPCI 103 "

HPC1 noom 4 23-Hb-S-38 HPCI 12b " X Torus Room 3 1-GG-S-101 - A HShV 135 " X Drywell 1-GG -S -101 -6 11SRV 135 " X LI 2well 1-GG-S-102-A HSRV 135 " X brywell 1-GG - S -10 2 -b MShV 135 " X Drywell 1-C" S-103-A MSR'? 135 " X Drywell 1-GG-S-103 -D HSRV 135 " X Drywell 1-GG-S-104-A NShV 135 " X brywell 1 uG-S-104 -o hShV 135 " X ul i ell 1-dG-5-105-a MSEV 135 " X bz). ell 1 -6G - S-10 5 -is MShV 135 X ur.-til 1-LG-S 400 s '- S h ', "

43L A 2,

  • 11

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P P \;*S UniR 2 TABLE 3.11.D.1 S a f "* v ;;ela t ej Shock Suppress 7rs (Snubbers)

SN'J DB ER IN HIGH (1)

PADIATION SNTIBBERS SNUBBERS SNUBEDS AREA ESPECIALLY INACCESSIBLE ACCESSIBLE StUlBETR DURING DIFFICULT DURING NOFMAL DURING NORMAL NU'1B ER LOCATION ELTVATION S HUTDCNN TO REMCVE OPERATION OPDATTON 1-Gr;-S- 10 6- B MSRV 135 See X Drywell 4.11.D.4.b 1-03-S-108-A MSRV 1 r:5 "

X Drywell 1-GG-S-109-B MSRV 145 "

X Drywell I-G3-S- 10 9- A MSRV 145 "

X Drywell 1-G3-S- 10 9- B MSRV 145 " X Drywell il-GG-S-110-A MSRV 145 " X Drywell 1-G G-S- 1 10- B MSRV 145 " X Drywell 1-GG-S-111-A MSRV 145 "

X Drywell 1 -GG-S- 1 1 1- B MSRV 145 "

X Drywell 1-GG-S-112-A MSRV 145

  • X Drywell 1-GG-S- 112- B MSRV 145 "

X Drywell 4

Notes for Table 3.11.D.1

1) Modifications to +his table due to changes in high radiation areas should be submi+tM to -h NFC as part of the next license amendment.

-2340-

PBAP3 6.O ADMINISTEATIVE CONTROLS 6.1 Responsibility 6.1.1 The Station Superintendent shall be responsible for overall facility operation. In the absence of the Station Superintendent, the Assistant Superintendent or the Engineer-Technical (or any other person that the Station Superintendent may designate in writing) shall, in that order, assume the responsibility for overall facility operation.

6. 2 Organization offsite 6.2.1 The of fsite organization for facility management and technical support shall be as shown on Figure 6.2.1.

hevisions to Figure 6.2.1 may be implemented without a prior License Amendment provided that a revised Figure 6.2.1 is included with the next License Amendment request.

Facility Staff

0. 2. 2 The facility organization shall be as shown on Figure 6.2.2 and:
d. Each on duty shif t shall be composed of at least the minimum shift crew compc 31 tion shown in Figure 6. 2.2
n. At least one licensed operator shall be in the control room and assigned to each reactor that contains fuel.
c. At least two licensed operators, excluding the operator on the second unit, shall be present in the control room during reactor start-up, scheduled reactor suutdown and during recovery from reactor trips.
d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor,
e. All COhE ALTERATIONS shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibility during this operation.
t. A fire brigade of at least 5 members shall be maintained onsite at all times. The fire brigade shall not include the minimum shif t crew necessary for safe shutdown of the unit (s) (3 members) or any personnel required for other essential functions during a fire emergency.

-243-

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BOARD OF DIRECTORS CHAIRMAN OF THE BOARD PRESIDENT AND CHIEF EXECUTIVE OFFICER EXECUTIVE VICE PRESIDENT AND CHIEF OPERATING OFFICER i

to -

F i

, OFFICE OF " DIE VICE PRESIDENT ELECTRIC PRODUCTION DEPARTMENT (1)

VICE PRESIDENT MANAGER I ,

GENERATION DIVISION (2)

EDSSIL-HYDRO NUCLEAR (1) Reports to the Chief SUPERINTENDENT SUPERINTENDENT Operating Officer STATION SUPERINTENDENT (2) Responsible for overall Fire Protection Program MANAGEMENT ORGANIZATION CHART PHIIADELPHIA ELECTRIC COMPAhY PEACH BOTIDM ATOMIC POWER STATION - UNITS 2 AND 3 FIGURE 6.2-1

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