ML20235C029

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Forwards Rev 5 to Environ Repts,Per Request to Jt Boettger. Matl Submitted W/Amend 13 Re Environ & Supplemental Environ Repts
ML20235C029
Person / Time
Site: 05000000, Hope Creek
Issue date: 11/15/1973
From: Schneider F
Public Service Enterprise Group
To: Purple R
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20235B454 List:
References
FOIA-87-554 8345, NUDOCS 8709240325
Download: ML20235C029 (49)
v • d • e


Text

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. O PSIEG Pubhc Service Electric t 3 Gas Cc :any 80 Park Place Newark, N J 07101 Phene 201/622-7000 November 15,1973 2

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AECE?v(f U. S. Atomic Energy Comission 50-854 0

' 8 78 '3 Mr. Robert Purple at 4 3

4315 St. Elmo Street 50-355 G

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Bethesda, Maryland 20014 Q

Dear Mr. Purple:

6 9

HOPE CREEK GENERATING STATION NOS. 1 AND 2 UNITS Per your verbal request to Mr. J. T. Boettger, we are sending you under separate cover 100 copies of the material submitted with our Anendment 13 for Hope Creek Generating Station pertaining to the Environmental and Supplemental Environmental Reports. This material is designated "Amendnent 5" to the Environmental P.eports.

Very truly yours.

uA..

. Schneider Man er of Engineering Electric Engineering Department 0.Jy 3

The Energy People 8709240325 870922 PDR FDIA em d72 MCCREAB7-554 PDR

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HOPE CREEK GENERATING STATION-L.

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NOS. 1 AND 2 UNITS DOCKET NOS. 50-354 AND 50-355

@"N AMENDMENT 13

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INTRODUCTION By letter of October 5,1973, the Atomic Energy Comission offered to provide an expedited staff review sucif that the application would.be ready for hearing within four months, if Public Service Electric and Gas Company (" Applicant") would agree to relocate the present Newbold Island Units 1 and 2 to the Artificial Island site in Lower A110 ways Creek Township, Salem County, New Jersey, where Salem Nuclear Generating Station Units 1 and 2 are currently under construction.

Public Service advised the' AEC of its decision to submit this amendment on October 19, 1973.

During the intervening period, discussions were held with the O.

Staff to determine the feasibility of the approach of incorporating the

. pertinent infonnation by referera from the Newbold and' Salem applica-tions in an amended application to permit such review. Amendment No. 13,

'which will relocate the Newbold Island physical pla'nt to the Lower A110 ways, Creek Township site,is submitted herewith under the following basic premises:

. 1.

The design of the Newbold Island Units remains unchanged except for appropriate modifications to adapt the station to the Salem j

site.

2.

In accordance with Section S0.32,10'CFR 50, there is incorpor-at.ed by refereau hercin t'.e techaicai 6:a p.c;cr.tly set forth c

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4 amended (Amendments 1-12), and Environmental and Supplemental Environmental Reports, as amended ( Amendment 1 h), for the

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Newbeld Island facil!. ties in Docket Nos.50-35L and 50-355, and in the Salem Nuclear Gen.erating Station Final Safety Analysis Report, as amended (Amendments 1-24), Appendix B and response to Q7.7 dated 4/68 of the Salem Nuclear Generating Station Preliminary Safety Analysis Report, and in the Environmental and Supplemental Er.viron-mental Reports, as amended (Amendments 1-3), (Docket Nos. 50-272 and 50-311), as sef; forth in the attached Hope Creek " Table of j

Contents" for thif, amendment.

1 I

3.

In any instance. where the available information in the reference is not wholly applicable or additional information is needed for this construction permit review, supplemental information is g

provided in the attachments to this Amendment No.13 or will be submitted in future amendments not later than Decenber 15, 1973, on a schedule agreed to with the Commission.

4.

The facilities are renamed " Hope Creek Generating Station, Nos.1 and 2 Uni ts. "

For the convenience of all reviewers, we have listed the sections incor-porated by reference to Docket No.s. 50-354 and 50-355 as "NIGS-PSAR,"

"NIGS-ER," anli "NIGS-SER" and to the Salem application (Docket Nos. 50-272 and 50-311) as "SNGS-FSAR" and "SNGS-PSAR," "SNGS-ER" and "SNGS-SER."

Where additional information is provided in this Amendment No.13, it is identified in the Table of Contents by providing reference to an attached document.

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'NOS 1 AND 2 UNITS

' PRELIMINARY SAFETY ANALYSIS REPORT x

T?.DLE OF CONTENTS.

t 1--INTRODUCTION AND

SUMMARY

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Reference

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NIGS SNGS ADD'TL PSAR FSAR INFO P

HShetion_

Title

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'Amd. 13' PROJECT' IDENTIFICATION ~>

Intro.

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METHODS OF'TSCHN[ CAL PRESENTATION

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I 1.2 Same DESIGN CRITERIA' 1.1_

1.3

-j SITE AND ENVIRONMENT

SUMMARY

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1.4 DESCRIPTION _

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'Same 5

STATION

SUMMARY

DESCRIPTION 1.5 Same MOMPARISON WITH LICENSES BWR UNITS 1,. 6 Same

SUMMARY

OF' RADIATION EFFECTS _

1. 7 -

Same

' CONDUCT OF OPERATIONS _

O

,1.8 Same QUALITY' ASSURANCE PROGRAM-1.9-

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Same RESEARCH AND~ DEVELOPMENT PROGRAMS _

'1.10-Same PROJECT ORGANIZATION 1.11

..'Same,

GENERAL CONCLUSIONS _

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PRELIMINARY SAFETY ANALYSIS REPORT s

TABLE OF CONTENTC o

2--SITE AND ENVIRONMENT l.

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S7ction Title PSAR FSAR INFO 2.1 SITE AND LOCATION

_ 2.2 Fig.A2.1-5 2.3

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2.2 POPULATION 2.4 A2.2.1

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, A2.2. 2 2.3 LAND USE 2.5 METE ROLOGY 2.6 2.4 2.5 EARTH SCIENCES 2.5.1 Geology 2.8 2.5.2 Seismology 2.9 2.6 HYDROLOGY 2.7 f

2.6.1 Surface Water 2.7.3 O 2.6.2 arouod W ter 2.7.2 2.6.3 Water Usage 2.7.1 2.7 ENVIRONMENTAL RADIATIO'.4 MONITORING 2.10 AND ECOLOGY 2.11 2.8 RADIATION EXPOSURE THROUGH THE 11.1.3.1 FOOD CHAIN j

2 App..- CONSULTANT REPORTS:

ENVIRONMENTAL STUDIES App. 2A...

CONSHT. TANT REPORT - MMEOROT.OGY App. A A7A.1 App. 2B' CONSULTANT REPORT - EARTH SCIENCES App.'B A2B.1 3

App. 2C CONSULTANT REPO!AT - LIQUEFACTION PSAR STUDIES Add'tl I

Info

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App. 2D CONSULTANT REPOR'P - MINIMUM & MAXIMUM A15.6.

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l WATER LEVELS

,ONSULTANT REPORT - WATER USAGE App. B App. 2E C

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PRELIMINARY' SAFETY' ANALYSIS REPORT

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TABLE OF CONTENTS l -REACTOR Ko f.::cr.::

NIGS FNGS

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.PSAR FSAR INFO-l 3.1

SUMMARY

DESCRIPTION SSame l^

,r 3.2 FUEL MECHANICAL DESIGN,.

Same 3.3

REACTOR VESSEL INTERNALS MECHANICALi Same l

DESIGN 3.4 REACTIVITY CONTROL MECHANICAL Same l-DESIGN.

l 3.5 CONTROL ROD DRIVE HOUSING SUPPORTS Same l

3.6 NUCLEAR DESIGN Same i

i 3.7 THERMAL AND HYDRAULIC DESIGN Same 3.8 STAND 3Y LIQUID CONTROL SYSTEM Same O

4--REACTOR COOtANT SvSTEM l

i

SUMMARY

DESCRIPTION Same 4.1 j

4.2 REACTOR VESSEL AND APPURTENANCES Same l

MECllANICAL DESIGN.

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4.3 REACTOR RECIRCULATION SYSTEM Same8 j

4.4 hDCLEAR SYSTEM PRESSURE RELIEF Same i

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SYSTEM
*. 4.,5

. MAIN STEAM LINE FLOW RESTRICTOR pane 4.6

-MAIN STEAM LINE ISOLATION SYSTEM Same

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REACTOR CORE ISOLATION COOLING Same SysTr" (rc-ac$

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Same l

4.8 RESIDUAL HEAT REMOVAL SYSTEM 5'

(1011.3 )

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PRELIMINARY SAFETY ANALYSIS REPORT TABLE OF CONTENTS I

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Reference NIGS SNGS ADD'TL re -i n Q:e PSAP

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4.9 REACTOR WATER CLEAMOP SYSTEM Same I

.t 4.10 NUCLEAR SYSTEM LEAKAGE, RATE LIMITS Same i

..iAND DETECTION) 4.11 MAIN STEAM LINES'AND FEEDWATER" Same EIPfNG I

8 5--CONTAINMENT

.5.1

SUMMARY

DESCRIPTION Same 5.2 PRIMARY CONTAINMENT Same 5.3 REACTOR BUILDING Same 5.4 CONTAINMENT

  • SYSTEM FABRICATION, Same (3

j ERECTION, TESTING AND INSPECTION 5.5 CONTAINMENT SYSTEMS MATERIAL Same SPECIFICATIONS AND QUALITY CONTROL s

5.6 PRIMARY CONTAINMENT PENETRATIONS Same l

AND ISOLATION I

5.7 PENETRATIONS AND ISOLATION OF THE Same i

l REACTOR BUILDING 5.* 8

. PRIMARY CONTAINMENT AND REACTOR Same

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BUILDING VENTILATION

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5.9 REACTOR BUILDING FILTRATION, Same RECIRCULATION, AND VENTILATION c

SYSTEM I

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5.11 ANALYSIS TO SUPPORT CONTAINMEN'T SEme 1

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PRELIMINARY SAFETY ANALYSIS REPORT

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S'ic tion _

Title

  • sSame ANALYSES TO SUPPORT SECONDARY l

5.12

' BARRIER-DESIGN BASIS Same

-5.13

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HYDROGEN GENERATION FOLL'OWING A LOSS OF COOL. ANT ACCIDENT l

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_--CORE STANDBY COOLING SYSTEM l

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Same SAFETY OBJECTIVES s

6.1 l'

Same SAFETY DESIGN BASIS l

6.2

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Same I

SUMMARY

DESCRIPTION _

~6.3 Same 6.4 pETAILED DESCRIPTION _

Same SAFETY EVALUATION _

( L5 Same INSPECTION AND TESTING _

l 6.6 l lame CONFORMANCE OF NEWBOLD ISLAND TO i

6.7 I

AEC INTERIM ACCEPTANCE CRITERIA l

FOR LIGHT WATER REACTORS

  • Same '

CORE STANDBY COOLING SYSTEM

~ 6.8 IMPROVEMENTS _

7--CONTROL AND INSTRUMENTATION-Same

SUMMARY

DESCRIPTION 7.1 Same P? ACTOR PROTECTION SYSTEM 7.2 Same PRIMARY CONTAINMENT AND REACTOR 7.3

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VE. SSEL If ^I ATION,

ev NG SYSTE.S Same M

.. CORE STA".ODY CCOLI 7.4

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' PRELIMINARY SAFETY ANALYSIS REPORT

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NIGS pHGS ADD'TL e=m ws ve

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7.;7 REACTOR MANUAL CONTROL SYSTEM Same 1

7.8 REACTOR VESSEL INSTRUMENTATION Same RECIRCULATION FLOW 10NTROL SYSTEM ir Same 7,9 7.10 FEEDWATER CONTROL SYSTEM Same t

l 7.11 PREtsSURE REGULATOR AND. TURBINE-Same GENERATOR CONTROL PROdESS RADIATION MONITORING

'Same 7.12 SYSTEM 7.13 AREA RADIATION MONITORING SYSTEM Same 7.14 HEALTH PHYSICS AND LABORATORY Same ANALYSIS RADIATION MONITORS PROCESS COMPUTER SYSTEM Same t'7.15

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7.16 NUCLEAR SYSTEM STABILITY ANALYSIS Same j

7.17

- UNIT CONTROL ROOM Same A7'.17..

s 8--ELECTRICAL SYSTEMS 8.1

SUMMARY

DESCRIPTION Same 8.2 GENERATOR Same Same A8.3.1 8.3 TRANSMISSION SYSTEM-I

'AB.4.I 8.4 AUXILIARY POWER SYSTEMS Same 1

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Sare A8.5.3 8.5 I ,*'

DISTRIBUTION-j

.35 '.5mLT A-7 ???E"U.*'?'???.'" ION PO E R Same 1

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Reference NIGS SNGS ADD'TL' S ction Title PSAR

'FSAR INFO 8.7 125 VOLT AND 250 VOLT D-C POWER

'Same SYSTDIS

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s, 3.8 24 VOLT.D-C SYSTEM Same 8.9 CABLE SYSTEM Same 9--RADIOACTIVE WASTE SYSTEMS 9.1

SUMMARY

DESCRIPTION AND DESIGN Same BASIS 9.2 LIQUID RADWASTE SYSTEM Same 9.3 SOLID RADWASTE SYSTEM Same 9.4-GkSEOUS RADWASTE SYSTEM Same A9.4,1 lO--AUXILIARY SYSTEMS

-10.1

SUMMARY

DESCRIPTION Same 10.2 NEW FUEL' STORAGE RACKS Same' 10.3 SPENT FUEL STORAGE RACKS Same

-10.4 TOOLS AND SERVICING EQUIPMENT Same 15.5 SPENT FUEL COOLING SYSTEM Same

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10.6 CHEMICAL TREATMENT A10.6

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STATION SERVICE WATER SYSTEM Same A10.7.1 10.8 REACTOR AUXILIARIES COOLING SYSTEM-Same 10.9 TURBINE AUXILIARIES COOLING SYSTEM Same

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PRELIMINARY SAFETY ANALYSIS REPORT TABLE OF_ CONTENTS J,

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10.10 FIRE PROTECTION SYSTEM, Same 10.11 AIR CONDITIONING, HEATING, COOLING, Same AND VENTILATING SYS'IEMS

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10.12 DEMINERALIZED WAT$R MAKE-UP SYSTEM Same 10.13 COMPRESSED AIR SYSTEM

'Same w

10.14

. POTABLE AND SANITARY WATER SYSTEMS

,Same 10.15 UNIT' EQUIPMENT AND FLOOR DRAINAGE Same SYSTEMS 10.16 PROCESS FAMPLING SYSTEM Same 10.17 COMMUNICATION SYSTEMS Same 0.18 LIGHTING SYSTEM

.Same 11-STEAM AND POWER CONVERSION SYSTEM 11.1-PERFORMANCE OBJECTIVES Same o

11.2 TURBINE GENERATOR Same j 11.3 MAIN CONDENSERS Same 1144 MAIN CONDENSER EVACUATION AND Same TURBINE SEALING SYSTEMS all.'5'

TURBINE BY-PASS SYSTEM

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Same

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11.7 c^"--~~.7-

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Same 11.8 CONDENSATE AND REACTOR FEEDWATE'R Saide l

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1 PRELIMINARY SAFETY ANALYSIS REPORT TABLE OF CONTENTS 12--STRU'CTURES AND SHIELDING

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NIGS FNGS ADD' E S ction Title PSAR FSAR INFO 12.1

SUMMARY

DESCRIPTION

'Same 12.2 PRINCIPAL PLANT STRUCTURES AND Same 5 '. 6. 2 A12.2.2 FOUNDATIONS 12.3 STATION SHIELDING DESIGN Same 13--CONDUCT OF OPERATIONS

13.1 INTRODUCTION

Same 13.2 ORGANIZATION AND RESPONSIBILITY Same 13.3 TRAINING Same 13.4 PREOPERATIONAL TEST PROGRAM Same 13.5 STARTUP kND POWER TEST PROGRAM Same 13.6 STATION OPERATION Same 13.7 RECORDS Same 13.8 OPERATIONAL REVIEW AND AUDIT Same i

13.9 HEALTH PHYSICS PROGRAM Same '

e 13.10 STATION ACCECS CONTROL 12.8 13.11

$:MERGENCYPLANS

_.12.9 A13.12

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14--SAFETY ANALYSIS 14.1 ANALYTICAL OBJECTIVE AND OUTLINE Same OF CONTENTS 14.2 UNIT SAFETY DESIGR BASES Saine

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PRELIMINARY SAFETY ANALYSIS REPORT

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TABLE OF CONTENTS j

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I Reference NICS SNGS ADD'TL Saction' Title PSAR

.FSAR INFO 14.3'

SUMMARY

OF RESULTS AND CONCLUSIONS

'Same 14.4 APPROACH TO SAFETY ANALYSIS Same

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14.5 ANALY$ES OF ABNORMAL OPERATIONAL Same TRANSIENTS

-14.6 Ai;AL'4 SIS OF LCSIGI' BASIS ACCIDE!;TS Came.

15--STATION DESIGN CRITERIA 15.1

SUMMARY

DESCRIPTION Dame 15.2~

CONFORMANCE TO AEC GENERAL DESIGN-Same CRITERIA 15.3 LOADING CRITERIA FOR THE NUCLEAR Same STLAM SUPPLY AND STATION DESIGN 15.4 INTEGRITY CRITERIA FOR PIPING AND Same EQUIPMENT PRESSURE PARTS 15.5 SEISMIC DESIGN' CRITERIA Same.

15.5. 2 Maximum Ground Accelerati.on and A15.5*

Response Spectra 15.6 WATER LEVEL DESIGN CRITERIA Same 15.6.1

' Introduction

.same A15.6.

2. 7. 3.'4 15.6.2 River Water Levels i

1st -Para

'15.6.3

, Maximum Anticipated Water Level A15.6.

... m, A15.6.

15.6.4 Minimum Anticipated Water Level.

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15.6.5 Water Level Relationships 2.7-1 A15.6.

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' PRELIMIllARY SAFETY ANALYSIS REPORT TABLE OF CONTENTS i

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Reference NIGS SNGS ADD'TL Saction Title PSAR FSAR INFO 15.7 WIND AND TORNADO DESIGN CRITERIA Same 15.8 UNIT SHARING AND INTERACTIONS Same i

a 15.9 ENGINEERED SAFETY FEATURE Same ENVIRONMENTAL. DESIGN CRITERIA I

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16--0UALITY ASSURANCE PROGRAM i

16.1 OVERALL APPROACH AND SCOPE Same A16.1 e

-16.2 PUBLIC SERVICE QUALITY ASSURANCE Same A16.1 i

.16.3 GENERAL ELECTRIC QUALITY ASSURANCE Same A16.1 PROGRAM j

16,4 CONSTRUCTION MANAGER QUALITY Same A1671 ASSURANCE l

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16.5 OPERATIONS OA Same A16.1

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17--TECHNICAL SPECIFICATIONS

17.1 INTRODUCTION

Same s

17.2 OUTLINE OF PROPOSED TECHNICAL Same l

. SPECIFICATIONS l

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-10 A2.2.1 MINIMUM EXCLUSION DISTANCE

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The revised station layout is shown in Figure A2.1-5.

4 As indicated'in the figure, the minimum exclusion diz.-.:.*

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-idd.'.:n;'_ ur.its It the *.rtif':ial Island site is approximately 2600 feet (

800 meters).

This' distance is measured from the edge of the reactor building which is closest to the porthern boundary of the site.

Distances,to the 'prope.

boundary in other directions are greater than 800 meters.

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.I Estimates of atmospheric dispersion factors as a

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function of distance frer the Artificial Isle.nd site o

are presented in Appendix A.1 of the Salem FSAR.

Using assumptions similar to those presented in the Salem FSAR, dispersion factprs have been estimated for the 800 meter minimum exclusion distance.

The projected cross-sectional area of the pdrtion of the reactor building above grade is the same as presented in the Newbold Island Preliminary Safety Analysis Report; 2800m2 The only difference is that two years of on-site data (6/69 to 5/71) were used in estimating the annual average dispersion factors for the Salem site.

The dispersion factor estimates are presented below (based on the 2800m2 cross-sectional area and a shape factor of 0.5).

O Least Favorable Diffusion Sequence - 800 Meters X/0 Time, Interval (sec/mJ) 0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4.5 x 10-4

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2 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.25 x 10-4 1 - 5 days 1.17 x 10-5 5 - 30 days 1.1 x 10-6 l

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A?A-1 AMENDMENT 13

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A2B.1 TEST BORINGS Reference is made to Salem PSAR Appendix B site studies in which boring logs covering the existing units are provid2d.

The Study Report includes the results of seismic refraction and shear wave velocity survey, static and physical tests of soil'and the testing method and pro-cedures.

The soil boring program will be extended to include' the taking of borings in the location of the additional units.

Borings Numbers 4, 6, 17 and 24 in the original report are in the area of the additional units, and indicate essentially the same soil conditions as are under Salem Units l'and 2.

As previously stated, additional borings will be taken 'to verify the subsoil conditions.

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At the completion of this program, the data will be submitted to the AEC.

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A7.17.1 HABITABILITY OF CONTROL ROOM, An accident in'either Salem Units 1 or 2 would not affect k

the habitability of the control rooms of the additional

units, n:p turcs to centr:1 re::.rerzennel would be kept below 30 rem - (thyroid)' and 5 rem (whole body) by Previding-appropriate recirculation and cleanup of the control room air volume through HEPA and charcoal

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A8. 3.1 TRANSMISSION SYSTEM DESCRIPTION Transmission system connections to the switching station are provided by tuo 500 FN lines and an everhead 500 EV tie to the existing 500 KV Salem Switchyard.

(See

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Figure A8.3-1, System Connection-Preliminary One-Line Diagram).

The preliminary transmission plan is to tie these lines to the Ne;w' Freedom Switching Station and a switching station in the Tuckerton area.

The lines are l

tied into the PJM network and each switching station has multiple high voltage connections to the grid.

l The plant switching station will be part of the Pennsylvania-New Jersey-Maryland Interconnection trans-mission system.

This system provides a highly reliable source of power for the operation of the station.

The multiplicity of connections f rom the system assures an-

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adequate supply of power for safe shutdown of the station.

The transmission lines, switching equipment and trans-formers are protected by high speed relays.

High speed breakers automatically isolate a faulted transmission line.

Energy from each unit's main step-up transformer feeds into the 500 KV switching station which consists of six 500 KV circuit breakers arranged in a breaker-and-a-half scheme.

A seventh 500 KV breaker is used for the tie to

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4 The 500-13.KV Station Power Transformers are connected t.o different bus sections of the 600 KV Switching Station.

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Each has the capacity to start.up both units at the same These tr:nsfor:'. rs feed a 13 KV ring bus as timo.

indicated in Figure AB.3-1.

The breakers-in the 13 KV ring-bus are normally operated such that each'500-13 KV transformer feeds two 13-6.9-4 KV Station Power Transformers ($ne for each unit)..

This arrangement assures a continuous preferred power supply to each unit in the event one 500-13 KV transformer should become inoperable.

If one of the 500-13 KV transformers is out of service, the 13 KV ring bus can be-closed and the remaining 500-13 KV transformer can supply-the four 13-6.9-4 KV transformers for the two units.

A tie to the existing Salem 13 KV ring bus will provide an additional supply to the ring bus.

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NVVW 500 KV.-13 KV.

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RING BUS

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500 KV-G KY.

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PtBLIC SERVICE ELECTRIC AND CAS COMPANY SYSTEM CONNECTION -

PRELIMINARY ONE LINE DIAGRAM PSAR-ANNDNENT 13 FIG.As,3-1 i

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A8.4.1 AUXILIARY POWER SYSTEM

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Auxiliary power for each unit's start-up, operation, and shutdown is provided by two 13-6.9-4 KV station power

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transformers, which are fed from the switching station.

These transformers replace the 230-6.9-4 KV transformers on Figure 0.4-1.

Two 6900 v and 4160 v group

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(auxiliary) buses are provided on each unit for normal operating loads, and four 4160 v vital b$ses are provided for engineered safeguard loads.

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.y AB.S.1 STANDBY A-C POWER SYSTEM DESIGN BASIS l (.

The standby a-c power system has the capability to cope with a postulated event involving a LOCA'in ene unit and a concurrent spurious ECCS actuation signal from the other unit, assuming the failure of a single-active component, other than the spurious signa,1.

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A9.4.1 POI!!TS CT r. ELE.'.SE k

Release of small amounts of gaseous radioactivity during normal operation will be directed through the unit vents.

The unit vent will run along side the edge,of the reactor building for each unit an.d discharge to the atmosphere.

For conservatism, no credit has been taken in the analysf.s of potential off-site exposures for this elevated rel' ease.

All e.stimates.of dispersion l

of routine releases were based on a ground level source.

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A9.4-1 M11;L:C;;T 13

o A10.6 CHEMICAL TREATMENT A10.6.1 SODIUM HYPOCHLORITE FEED No bulk elemental chlorine will be used or stored at the l

plant site.

Sodium hypochlorite will be used for chlorina-tion of circulating and service water systems.

This l

material will be received as a 15 percent liquid solution and will be stored outdoors in tanks within a diked area.

Any accidental release or~1eakage from the storage tanks will have no effect on the ability to shut-down the plant in a safe manner and maintain it in a safe condition.

Organic fouling in.the service water system will be controlled by injection of sodium hypochlorite (15% solution) diluted with station service water.

(See Section 10.7 Station Service Water System).

The station service water system cooling water circuits for the reactor and turbine auxiliaries will be chlorinated for one-half hour periods three times a day.

The feed rate of sodium hypochlorite will be controlled by monitoring free chlorine residual at the outlet 'of the final system h' eat exchanger.

Organic fouling in the condenser cooling water system will also be controlled by periodic injection of dilute solutions of sodium hypochlorite.

(See Section 11.6 Circulating Water system).

The solution will be discharged through a distribu-tion pipe at the cuction of the circulating water pumps.

Duration of injection will be controlled by monitoring the free chlorine residual in the circulating water return to the tower.

A10.6.2 CIRCULATING WATER pH-ALKALINITY CONTROL Requirements for pH-alkalinity control are being reviewed and will be submitted later.

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A10.6-1 AMENDMENT 13 l

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A10.7.1 SERVICE WATER SYSTEM WATER SUPPLY

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l The Service Water pumps will be set low enough.to

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provide adequate submergence for a minimu:'. water 1

level of 76 '-0" P.S. datum (El. 89 '-9" Marcus Hook l

1 Datum) to assure safe shutdown -of the plant.

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A10.7-1 AMP!'D!"T.? T

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11.6 CIRCULATING WATER SYSTEM The general description of the circulating water

- system as discussed in Section 11.6 of the NIGS-PSAR-is applicable.

Supplementary detailed information will be submitted later.

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u-A12.2.1 FOUNDATIONS _- GENERAL t

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Section 5'. 6.2 of the Salem FSAR is applicable to the.

reldcated units with the exception of the last two sentencesi of the first paragr6ph which should be deleted.

Information corresponding to Figure 5.6 d and Table 5.6-1 will be, submitted at a later,date.

u The bSttbm of the reactor building base' mat is located at Eleva. tion +34.0 feet.

The base mat is sitting on top

\\ of the'kean concrete fill.

)( The bottom elevations of.the auxiliary building and r

3

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turbine generator area base mats will be determined later.

  • These blise mats also f;it on top of the lean concrete fill.

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g Piles for the cooling tower columns and pump structures

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will be driven to the Vincentown formation instead of

',the,Rariban formulation as mentioned in the Newbrid

'Islandh PGAR.

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The servf,ce water intake is.also supported directly on Vincemtown formation'instead of Raritan formation l

4 as mentioned in the PSAR.

Information on the construction of foundations (12.2.11) and foundations for the cervice' water piping (12.2.12) will

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.be submitted at a later date.

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4 A13.11.1 EMERGE"CY PLM:S 1

A comprehensive emergency plan for the Salem Generating Station Units 1 and 2 has been presented in Section 12.9 of the Salem Final Safety Analysis Report.

This plan is considered applicable to the relocated units, subject to any differences arising from'PWR versus BWR operation.

' The plant related design and operational information is contained in the Newb'old Island Docket (50-354/355).

The emergency plan will be revised, as necessary, to accommodate the rolocated units on the Salem site.

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Id5.11-1 I'

D:::::T 13

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A14.6.1 SArrTY A::ALYSIS k

The radiological analysis of design basis accidents presented in Section 14 of the NI-PSAR was based on a l-l 700 meter minimum exclusion distance, a one mile low population zone, and. meteorologic,a1 dispersion factors appropriate to the Hewbold Island site.

As the minimum exclusion distance has been increased to 800 meters, the low population zone h'as been increased to five miles and l

atmospheric dispersion is more favorable at the Artificial Island site, all exposures reported in Section 14 (and other sections) are conservative.

As a result, the radiological exposure calculations are not l

being revised.

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A14.C-1 AMrND!'? T 13

.A15.5.1 SEISMIC DESIGN CRITERIA

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Reference to Taf t accelogram in Section 15.5.2 of the Newbold Island Preliminary Safety Analysis Report

.should be changed to El. Centro 1940 accelogram.

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addition,' bolted and riveted assembly dampings are now 41 and 7% res'pectiv'ely.

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Al5.5-1 A M E M M ir!'T 3 3 3

A15.6.1 WATER LEVEL DESIGN CRITERIA' The plant grade for the relocated units will be +10.5

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Coast and Geodetic Survey Mean Sea Level Datum rather that +25.0 as stated in NIGS-PSAR.

The same methods and techniques as were used to ascertain

' the water level and dike requirements for the original Salem Units 1 and 2 will be employed.

Our consultant's report on Water Level and Shore

  • Protection for the relocated units will be submitted at a later date.

The datum and water level relationships shown on Figure 2.7-1 Amendment 14 of SNGS-FSAR are applicable to the relocated units with the exception of Flood Protection Level for Safeguard Systems and the Low Low Water Design.

The Low Low Water Design will be 76'-0" PSE&G Datum.

The Flood Protection Level will be given O

in the coa uitent' reeort mentioaed ebove.

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A16.1 pUALITY ASSURANCE PROGRAM

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L The Quality Assurance program described in NIGS-PSAR is applicable, hcweter, the information is not-set forth in relationship to the 18 Criteria in Appendix B l

of 10 CFR 50.

This correlation will be provided later.

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HOPE CREEK GENERATING STATION NO. 1 AND 2 UNITS ENVIRONMENTAL REPORT il' TABLE OF CONTENTS

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Reference Additional Section Title.

NIGS-SER SNGS-SER Information I.

S UPHARY................

I II.

INTRODUCTION A.

Statement of Project Same B.

Purpose..............

Same C.

Nuclear Generating Station Descrip-tion Same III.

ENVIRONMENTAL STATEMENT A.

Probable Environmental Impact 1.

General............ Same 2.

Themal Effects........

4 3.

Cooling Tower Effects.....

5 4.

Radiological Effects Same 5.

Chemical Effects Same O

6.

Physical Presence.......

7 7.

Land Use III.A.6 8.

Other Areas of Possible Envi-ronmental Impact....... Same B.

Possible Adverse Environmental Effects.............. Same

.C.

Alternatives to the Proposed Plant 1.

Future Power Needs Same 2.

Importation of Power Same 3.

Fossil-Fuel Plant....... Same 4.

Gas Tu rb i ne.......... Same D.

Comitment of Resources and Enhance-ment of Long-Term Pmductivity Same E.

Irretrievable and Irreversible Uses of the Environment Same F.

Pollution Control Measures 1.

Construction 11A-C 2.

Plant Operation........ Same I

G.

Agencies from which Licenses and Per its are Required III.G i

Amendment 5

I TABLEOFCONTENTS(cont'd) i

)

Reference Additional

(.

,Section Title NIGS-SER SNGS-SER Information

]

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IV.

BACKGROUND INFORMATION

.]

A.

Description of Plant Site.....

IV.A 1

l 1.

Location IV.A.1

)

2.

Land Use III.A.6 j

3.

Population IV.A.3 4.

Geology and Seismology IV.A.4 5.

Hyd rol ogy...........

IV.A.5 1

6.

Meteorology..........

IV.A.6

a. General Meteorological Features Appendix A.1
b. Micrometeorology......

Appendix A.1

c. Planned Meteorological Tower Facility Appendix A.1
d. Joint Frequencies of Wind Speed, Direction and Sta-bility Categories.....

Appendix A.1 6.

Description of Plant Effluent and Waste Systems 1.

Service Water System 29 O

a. General Description
b. Water Sources
c. Discharge System.

(1) Thennal Releases....

(2) Chemical Releases 2.

Circulating Water System 31E 3.

Radioactive Waste System Same

a. Liquid Radwaste Same
b. Gaseous Radwaste...... Same
c. Solid Radwaste....... Same 4.

Other Effluents

a. Non-nuclear Regenerative W as t e...........

35

b. Potable and Sanitary Water. Same i

C.

Description of Environmental Studies 1.

Environmental Radiation Moni-toring Program 2.10 (Salem FSAR) 2.

Ecology Program........

2.11 (Salem FSAR) 3.

Meteorological Studies Appendix A (Salem FSA 4.

Cooling Tower Plume Studies..

41 S.

Thennal Studies........

41

)

6.

Radf ation Exposure Through the

)

Food--Chain 11.1.3.1(SalemFSAR) ii Amendment 5 w________-______

I.

St# NARY t

This Amenhent to the Environmental Report and Supplemental Environmental l

Report reflects the relocation of two nuclear units from Newbold Island to the Artificial Island site in Lower Alloways Creek Township, Salem l

County, New Jersey. The site is situated on a 700-acre tract commonly known as Artificial Island and is located on the Delaware River approxi-mately 70 miles south of Neubold Island. The service dates for the two relocated units are scheduled for May 1981 and May 1982.

The contents of the existing Sumary discussion are generally applicable with regard to the relocated units. The design of the plant remains unchanged except for required modifications to adapt the station to the new site. In cases where available infomation is not wholly applicable O

or additional information is needed for this construction pemit review, supplemental information is provided in the attachments to this Amendment No. 5 or will be submitted is future amendments not later than December 15, 1973 on a schedule agreed to with the Comission.

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I Amendment 5

III.A.2 Thermal Effects The operation of the circulating water systems and the service water b

systems are described in Part IV B of this report. The use of natural draft hyperbolic cooling towers to dissipate waste heat will result in minimal thennal effects upon the environment. Studies are being con-ducted to investigate the dispersion characteristics of the heated discharge to the Delaware River. A discussion of this study will be

< d mitted later.

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4 Amendment 5 l

III.A.3 COOLING TOWER EFFECTS 1.

The probable. evnironmental effects of' cooling towers at the Artificial

(

Island site is not expected.to p oduce any significant effects as a result l

of plant operation. The utilization of natural draft cooling towers for l

brackish water service will be analyzed by Maynard E. Smith of Smith-Singer, Meteorologists, Inc. in the nenner necessary to assure the suitability of the proposed cooling system design with the environs.

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5 Amendment 5 g,.

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Ill.A,6

. Fnysical P'ruence The picci,.ill be e elecn, functionsily and esi:%tict'ly plecting dw: p

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that Will bicnd 6: hermaicusly as possible witi thc 5 p rounding.

re to the aht".ce of bulk fuel stcrage anJ handiir,; facilities, the unit vill be irgrovad in eppearance when compared to fossil fusled plants. The hyperbolic cooling. towers are designed to be aesthetically pleasing.

Every effort wil9 be made to minimize changes to the terrain end the vegetation et the site.

All foliage, bulkheads, rip-rap and jetties, except those in the actual construction areas, will be left intact.and any removed from the shore lines for construction will be replaced by suitable shore protection materials.

In addition to the architectural treatment of the plant buildings the Q

general site areas adjacent to the buildings will be completely graded with some landscaping to enhance the plant appearance.

It is the opinion of the applicant that the physical presence of Hope Creek Generating Station will have nc significant adverse effect oc the use of the surrounding area.

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faendment 5

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III.F.1 Construction

. Durin the initial constr/. Hon phtse, portOb scii-conteined :t;.ic :pt c,

will be empicyed to cor; tit saliitory wastes.

During the major cc s trucuo

~

a temporary toilet and ucsh 'touse will bc 'onstructed and will cis chuge te c

s septic tanks and a temporarf septic field.

No waste will go into the rivc.

-The material from the excavnion will be deposited on approximately 150 acres of aarshy ground east of the site. Some mcterial will event.; ally be removed and used as backfill. A dewatering system will be installed around the excavation and shall be capable of drawing the grounicater. level down to approximately 75 feet below grade.

Observe. tion wells will also be-installed at different distances from the excavation. These observation wells will be used to measure the ground water levels to demonstrate that the existing wells in the vicinity wi~ll not be affected.

A concrete batch plant will be constructed which will be 60 feet high and will be located at a point approximately 600 feet from the shore line.

The aggregate piles which will be adjacent to the batch plant will be limited to a maximum height of 30 feet.

Dust collectors and air filters will be installed on the batch plant to minimize cement dust or fly ash which is mixed as an additive in the concrete from entering the atmosphere. The aggregates and sand will be free from any particles which could cause

' dust to enter into the ' air.

All fine-particled materials such as cement and fly ash used in the concrete will be placed in ~ bins or blimps. The batch i i ', F o x,

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11A Amt.ndrent 6 i

There will be no concrete or water cement mixtures dumped into the river or indiscretely dumped on land.

There will be a spoils area designated

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for the disposal of weste concrete mixtures on the island. With the above 1

ineasures all aspects of this phase of operation have been considered so that there will be no adverse effect on the environment.

t 4

During the initial phases of the construction of the cooling towers and switchyard, piles will have to be driven for the support of these struc-tures.

Some noise will be proQced but since the site is relatively remote it should not be objectionable.

The nearest resident is sufficiently far enough away so that no noise or little noise will be perceived.-

For use during construction of the plant, temporary buildings will be erected on the site. They will generally be one-story metal buildings C

attractively painted to produce a pleasing effect when seen.

Erection of these buildings will start in the summer of 1974.

E Of all the facilities that will be temporarily constructed or used during construction, the only items that will be visible from afar are the construction cranes.

I i

For the construction of the cooling towers, two tower cranes projecting

)

up to 50'0 feet above the site elevation will be utilized. Two gantry j

l cranes will protrude approximately 275 feet above the site grade e'tevation and several smaller cranes (175 feet high booms) will be included. The crenes are constructed of slender nem!'e s which u"' ninimite their presence.

11B Am:nd nent 5

N h

Dre@rc for the sen'cr wate..intalt 6nd duda,p Mil 6: :

.t to entrt.r:-

mately'30,000 tubic y rds c/ naterial. All dredged taterial-will be j

depcsited within dites in eie spoil eree at'the north end of the site.

A sluice box of stannr: design will be utilized to prevent excessive sus-pended materials fro; returning to the river.

The service water intake structure, which will be located at the water-front, will be substantially submerged.

The pumps and motors will be housed in a structure that will be architecturally designed to produce a pleasing scene when. viewed from the river.

Since the major portion of this structure will be submerged, temporary cofferdams will have to

. be erected during the construction of. this facility. The presence of the cofferdams will be minimized as they will project only a. few feet above the high water level and will be removed upon completion of construc-h tion of tnis facility.

1 4

l Dredging time will be restricted to the non-critical months as required i

by the. Delaware River Basin Cocenission regulations (dredging is permitted during July, August, September, December, January and February). No i

significant effects on the important commercial or game fishes are expected j

and any temporary displacement of other population will not be ecologically significant.

i 11C Amendment 5 i

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' IV.E.1 Service Water System The information in Section; B.1 a, b and c pertaining to the ger,erci

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arrangement of the service water syste, wSter sources, and the dischirg:

j i

system, respectively, are for the most part a;0licable.

Supplemental i

detail infomation on flows, concentrations cnd thermal releases based j

e on the use of brackish water for cooling tower make-up will be submitted later.

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29 Amendment 5

IV.C.2 Circui:tir.g Water Systcn The ceneral arranrem:nt of the closed-loop circulatir; water system,

(

as described, re iins enchenged.

Due te the nature tf the Delaware River weter qutlity at the Artificial Isicnd site it is anticipated that the circulating water system will be operated at a level of approximately tuo concentrations.

Finalization of tttal makeup water requirements to compensate for evaporative losses anc blowdown require-mtnts will be submitted pending the completion of antlyses for all ranges of system operation.

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31E Amendment 5

IV.B.4a Hon-fluclear Regenerative pcste The general discussion of the nor. radioactive chemical liquid effluern

. g remains unchanged with respect

+a tl e systen description and is appli:nk for the relocated units at the Artificial Island site.

The de:nineral':er I

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plant input requirements and effluent wastes shall be described in a I

supplemental discussion.

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35 Amendment E I

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t IV.C.4' Cooling Tower Plume Studies IV.C.5 Thernal Studies l

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l The general intent of the above subject studies, as described, is applicable to the relrected utilts.

Correspondir; enalyses by consultants in the fields of meteorology and hydrology will be performed for the Artificial Island site to assure the suitability of system operation with the environment.

The results of these stucies will be submitted in a supplemental discussion.

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41 Amendment 5 4

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