Text

Proposed Tech Specs Re Defueled Facility OL
	ML20005F248
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	01/05/1990
From:	; LONG ISLAND LIGHTING CO.
To:	;
Shared Package
ML20005F164	List: ML20005F163; ML20005F246; ML20005F248; ML20005F251;
References
	NUDOCS 9001160089
	Download: ML20005F248 (95)
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I ATTACHMENT 2 TO SNRC-1664 ;

! Proposed Revision to NPF-82 and Technical Specifications

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9 '_LONG-ISLAND LIGHTING _ COMPANY

_ DOCKET NO. 50-322 SHOREHAM NUCLEAR POWER STATION, MI_T 1 DEFUELED FACILITY OPERATING LICENFE License No. NPF-82

1. - The Nuclear Regulatory Commission (the Commission or the NRC) has

, found that:

A. The application for a license filed by the Long Island _ Lighting Company (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I, and all required modifications to other agencies or bodies have been duly made; B. Construction of the Shoreham-Nuclear Power Station, Unit 1 (the facility), has been completed in conformity with Construction

,ew Permit No. CPPR-95 and the application, as amended, the l) u provisions of the Act, and the regulations of the Commission; C.-

The facility will operate in conformity with the application, as j amended, the provisions of the Act, and the regulations of the

~ Commission; D. There is reasonable assurances (i) that the activities <

authorized by this operating license can be conducted without endangering the health and cafety of the public, and (ii) that ,

such activities will be conducted in compliance with the i

' Commission's regulations set forth in 10 CFR Chapter I; l E. The license is technically qualified to engage in the activitics ,

authorized by this-cperating only license in accordance with the l Commission's regulations set forth in 10 CFR Chapter I; F. The licensee has satisfied the applicable provisions of 10 CPR l 140, " Financial Protection Requirements and Indemnity j Acreements," of the Comminsion's regulations; G.

The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public;

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"H.' - Af ter weighing the environmental, economic, technical, and .other 1

j benefits of the facility aoainst environmental and other costs and considering available alternatives, the issuance of Facility

. Operating License No. NPF-82, subject to the conditions for i protection of the environment set forth in the Environmental Protection Plan attached as Appendix D, is in accordance with 10 CPR Part 51 the Commission's reculations and.all applicable

-reauirements have been satisfied; and I.- The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this license will be in accordance with the' Commission's reculations in 10 CFR Parts 30, 40, and 70.

2 Based on the forecoing findinas and the Concluding Partial Initial Decision issued by the Atomic Safety and Licensina Board on September 23, 1988, 1/ Defueled Facility Operating License No. NPF-82 is hereby issued to the Long Island Lightina Company (the licensee) to read as follows:

P A. The license applies to the Shoreham Nuclear Power Station, Unit' '

(~ 1, a boiling water nuclear reactor and associated equipment,

(_]f owned by the 1licensee. The facility is located in Suffolk County, New York, and is described in the licensee's Defueled Safety Analysis Report (DSAR), which includes, by reference, the appropriate-sections of the Updated Safety Analysis Report (USAR),

as supplemented and amended, and the licensee's Enviroamental Report, as supplemented and amended.

B. Subject to the conditions and requirements incorporated herein,

-the Commission hereby licenses the Lono Island Lighting Company (LILCO, the licensee):

(1) ~ Pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use, but not operate the facility at the designated location in Suffolk County, New York, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, to possess special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for one reactor core load as described in Defueled Safety Analysis Report, as supplemented and amended; L 1/ See also: Partial Initial Decision, LBP-83-57, September 21, 1983; ALBA-788, October 31, 1984; Commission Memorandum and Order, CLI-84-21, November 21, 1984; Memorandum and Order Ruling on Remand l .I~h Issues, LBP-84-53, November 30, 1984; Partial Initial Decision on b- Emeroency Diesel Generators, 85-18, June 14, 1985; Partial Initial Decision on Emergency Plannino (EP), LBP-85-12, April 17, 1985; Concludina Partial Initial Decision on EPy LBP-85-31, Auaust 26, 1985; LBP-87-30, November 6, 1987; CLI-87-12, November 5, 1987; Partial Initial Decision (EP), LBP-88-13, May 5, 1988; LBP-88-24, September

23, 1988; CLI-89-02, March 3, 1989.

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1 (3)- Pursuant to the Act and 10 CFR Parts 30, 40, and'70, to possess, any byproduct, source and special nuclear material I as sealed neutron sources for reactor startup, sealed !

neutron sources-for reactor instrumentation and radiation I monitoring equipment calibration; and as fission detectors l in amounts as required. l (4). Pursuant to the Act and 10 CFR Parts.30, 40,_and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for rample analysis or instrument calibration or associated with -

radioactive apparatus or componente; and (5) Pursuant to1the Act and 10 CFR Parts 30, 40, and 70,-to i possess; but not separate, such hyproduct and special >

nuclear materials as may be produced by the operation of the facility.

C. This license shall be deemed to contain and is subject-.to the conditions specified in the Commission's regulations set forth'in' 3e't 10 CFR Chapter I and is subject to all applicable provisions of

(_) the Act and-to the rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions incorporated below:

(1) . Maximum Power Level The licensee is not authorized to' operate the facility at any core power level.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications centained in Appendix A and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. The licensee shall maintain the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Recuirement to Obtain NRC Approval to Place Fuel in the Reactor Vessel The licensee shall not place any fuel assemblies in the reactor vessel without the prior approval of the NRC Staff.

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D. The licensee shall implement and maintain in effect'all provisions of the approved fire protection-program an described in the' Fire Hazards Analysis Report and the Defueled Safety Analysis Report for the facility and as approved in the SER dated 4/81 and Supplements 2 dated 2/82 and 9 dated 12/85, subject to the following provisiont The licensee may make changes to the approved fire.

protection program without prior-approval of the Commission only if these changes would not adversely affect the ability to maintain the fuel in the Spent Fuel Pool in a safe condition in the event of a fire.

E. The' licensee shall fully implement and maintain in effect all i provisions of the Commission-approved physical security, guard ;

training and qualification, and safeguards continaency' plans including amendments made pursuant to provisions of the ,

Miscellaneous Amendments and Search Requirements revisions to 10 ;

CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR'73.21, are entitled: "Shoreham rg Nuclear Power Station Security Plan For Fuel Storace in the Spent

(_j - Fuel Pool," as submitted January-5, 1990; the "Shoreham Nuclear Power Station Guard Training and Qualification Plan," with revisionn submitted through December 14, 1988; and "Shcreham Nuclear Power Ftation Safeguards Contingency Plan," with revisions submitted through May 13, 1988. Changes made in accordance with 10 CPR 73.55 shall be implemented in-accordance with the schedule set forth therein.

F. Except as otherwise provided in the Technical Specifications or Environmental Protection Plan, the licensee shall report any violations of the requirements contained in Section 2.C of this license in-the following manners initial notification shall be made within twenty four (24) hours to the NRC Operations Center via the Emergency Notification System with written followup within 30 days in accordance with the procedures described in 10 CFR 50.73 (b) , (c), and (e).

G. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic L'nergy Act of 1954, as amended, to cover public liability claims.

H. This license supersedes Facility Operating License No. NPF-36, dated July 3, 1985.

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'l "- I.. . This licen.se' is effective as of the date of insuance and shall .

-l expi;e at midnight lon-April 13, 2013.

, FOR.THE NUCLEAR REGULATORY COMMISSION i

Thomas E. Murley, Director Office of Nuclear' Reactor Regulation Attachments:

1.= Appendix A - Technical Specifications (NUREG-1357)

2. Appendix B' . Environmental Protection Plan Date:of Issuance l

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NUREG-1357 i

TECHNICAL SPECIFICATIONS Shoreham Nuclear Power Station, J Unit No. 1 Docket No. 50-322

' Appendix "A" to ;

License No. NPF-82 !

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t ' N INDEX l DEFINITIONS-t, SECTION, .
l l PAGE-
'1.0 ' DEFINITIONS l
L 1.1 ACTION...................................................... 1-1 1.2- CHANNEL' CALIBRATION......................................... 1-1 ,
1.3 LCHANNEL CHECK......,........................................ 1-1 L
1.4 CHANNEL FUNCTIONAL TEST..................................... 1-1 1;
L 1.5 F RE Q U EN C Y N O TAT I ON . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.6 . MEMBER (S)'OF THE.PUBLIC..................................... 1-2 1'
1.7 OFFSITE DOSE CALCULATION MANUAL (ODCM)......................-1-2 '
. (_,.
f~) B -OPERABLE - OPERABILITY...................................... 1-2 1.9 PROCESS CONTROL PROGRAM (PCP)............................... 1-3 1
.1.10 REPORTABLE EVENT............................................ 1-3 1.11 SECONDARY CONTAINMENT INTEGRITY............................. 1 1.12. SITE BOUNDARY............................................... 1-3 1.13 ' UNRES TRI CTED A REA . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-4
'l
- g SHOREHAM - UNIT 1 i
4 _
1 .
.x
,1 INDEX- ,
l i LIMITING CONDITIONS FOR FUEL HANDLING OPERATION & SURVEILLANCE REQUIREMENTS' SECTION: ,
PAGE.
2.0 SAFETY. LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2-1
.3/4.0 APPLICABILITY.................................... 3/4 0 3/4.1 INSTRUMENTATION 3/4.1;l MONITORINGiINSTRUMENTATION-
' Radiation Monitoring Instrumentation............ 3/4 1 o Seismic Monitoring Instrumentation.............. 3/4 1-6 Meteorological Monitorina Instrumentation....... 3/4 1-9 3/4.2 CONTAINMENT SYSTEMS 3/4.2.1 SECONDARY CONTAINMENT Secondary Containment Integrity................. 3/4 2-1
TO .
\/4.3' PLANT SYSTEMS 3/4.3.1 SEALED SOURCE CONTAMINATION....................... 3/4 3-1 t
'3/4<3.2 SETTLEMENT-OF REACTOR BUILDING Total Settlement.................................. 3/4 3-3 Differential Settlement Across The Structure..... 3/4 3-4 Penetration Differential. Settlement.............. 3/4 3-5
~\
SHOREHAM - UNIT 1 11
~t
, INDEX
' LIMITING CONDITIONS FOR FUEL HANDLING OPERATION & SURVEILLANCE REQUIREMENTS
, i SECTION PAGE i 3/4.4 ELE _CTRICAL POWER SYSTEMS 3/4.4.1 A.C. Sources.................................... 3/4 4-1 ;
'3/4.4.2 ONSITE POWER DISTRIBUTION SYSTEMS................ 3/4 4-2 1
3/4.5 FUEL HANDLING OPERATIONS '
3/4.5.1 COMMUNICATIONS................................... 3/4 5-1 ;
i 3/4.5.2 REFUELING PLATFORM............................... 3/4 5-2 !
i 0
3/4.5.3 CRANE TRAVEL..................................... 3/4 5-4 3/4.5.4 WATER LEVEL - SPENT FUEL STORAt;E POOL........... 3/4 5-5 3:W PASES
.r,
--s/4.0 APPLICABILITY.................................... B 3/4 0-1 l 3/4.1 INSTRUMENTATION s
t 3/4.1.1 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation............. B 3/4 1-1 Seismic Monitoring Instrumentation............... B 3/4 1-1 Meteorological Monitorina Instrumentation........ B 3/4 1-1 3/4.2 CONTAINMENT SYSTEMS 3/4.2.1 SECONDARY CONTAINMENT Secondary Containment Integrity.................. B 3/4 2-1 l
l HOREHAM - UNIT 1 111 Q _ _ -
.h,b' .
i d
N.) ,
INDEX /
n n l BASES
]
1 SECTION PAGE 3/4.3 PLANT SYSTEMS 3
i 3/4.3.1 SEALED SOURCE CONTAMINATION...................... B 3/4 3-1 3/4.3.2 SETTLEMENT OF REACTOR BUILDING. . . . . . . . . . . . . . . . . . . B 3/4 3-1 3/4.4' ELECTRICAL POWER SYSTEMS 3/4.4.1 A.C. SOURCES..*................................... B 3/4.4-1 3/4.4.2 Distribution Systems............................. B 3/4 4-2 3/4.5 FUEL HANDLING OPERATIONS :
3/4.5.1 COMMUNICATIONS................................... B 3/4 5-1 r 4.5.2 REFUELING PLATFORM............................... B 3/4 5-1 j
/4.5.3 CRANE TRAVEL..................................... B 3/4 5-1 j 3/4.5.4 WATEP LEVEL - SPENT FUEL STORAGE POOL............ B 3/4 5-1 ,
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INDFX ,
DESIGN FEATURES o SECT.lgN c
PAGE 5.1 SITE !
Exclusion Area........................................ 5-1 :
Low Population Zone................................... 5-1 j SITE BOUNDARY for Radioactive Gaseous and Liquid ,
Effluents........................................... 5-1 i'
5.2 CONTAINMENT Confiauration......................................... 5-1 ,
Design Temperature and Pressure....................... 5-1 Secondary Containment................................. 5-2 l 5.3 REACTOR CORE i Fuel Assemblies....................................... 5-6 l
Control Rod Assemblies................................ 5-6 5.4 REACTOR COOLANT SYSTEM Design Pres sure and Temperature . . . . . . . . . . . . . . . . . . . . . . . 5-6 ,
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I 5.5 METEOROLOGICAL TOWER LOCATION.......................... 5-7 l
5.6 TUEL STORAGE Criticality........................................... 5-7 Drainage.............................................. 5-7 l Capacity.............................................. 5-7 l
l 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT.................... 5-7 l
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INOEX ADMININSTRATIVE CONTROLS ECTION PAGE 6.1_ RESPONSIBILITY............................................... 6-1 6,2 ORGANIZATION................................................. 6-1 6,2.1 NUCLEAR ORGANIZATION.................................... 6-1 6,2.2 UNIT STAFF.............................................. 6-2
.6.3 UNIT STAFF QUALIFICATIONS.................................... 6-3 6.4 TRAINING..................................................... 6-3 6.5 REVIEW AND AUDIT 6.5.1 REVIEW OF OPERATIONS COMMITTEE (ROC).................... 6-3 FUNCTION................................................ 6-3 COMPOSITION............................................. 6-3 ALTERNATES.............................................. 6-3
[" MEETING FREQUENCY....................................... 6-3 QUORUM.................................................. 6-4 RESPONSIBILITIES........................................ 6-4 RECORDS................................................. 6-5 6.5.2 NUCLEAR REVIEW BOARD.(NRB).............................. 6-6 FUNCTION................................................ 6-6 COMPOSITION............................................. 6-6 ALTERNATES.. 2.......................................... 6-6 CONSULTANTS............................................. 6-6 MEETING FREQUENCY....................................... 6-6 QUORUM.................................................. 6-7 REVIEW.................................................. 6-7 AUDITS.................................................. 6-7
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RECORDS................................................. 6-8 SHOREHAM - UNIT 1 vi
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. l ADMININSTRATIVE CONTROLS j F.ECTION PAGE l l
1 6.6 REPORTABLE EVENT ACTION...................................... 6-9 ;
I 6.7 PROCEDURES AND PROGRAMS..................................... 6-9 I 6.8 REPORTING' REQUIREMENTS....................................... 6-13 1
6.8.1 ROUTINE REPORTS......................................... 6-13 .
J ANNUAL REPORTS'.......................................... 6 P ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT...... 6-13 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT.......... 6-14
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6.8.2 SPECIAL' REPORTS......................................... 6-14
/~T RECORD RETENTION............................................ 6-14 U. 9 6.10 RADIATION PROTECTION PROGRAM................................ 6-15 .
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6.11 HIGH RADIATION AREA......................................... 6-16 6.12 PROCESS CONTROL PROGRAM (PCP)............................... 6-17 6.13 OFFSITE DOSE CALCULATION MAN,UAL (ODCM)...................... 6-17 O
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INDEX ,
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- LIST OF FIGURES 1 I
FIGURE PAGE !
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' 5.1.1-1 EXCLUSION AREA........................................ 5-3 l
5.1.2-2 LOW POPULATION ZONE................................... 5-4 I 5.1.3-1 SITE BOUNDARY.FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS............................................. 5-5
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' k- INDEX LIST OF TABLES ,
TABLE PAGE j 1.1- SURVEILLANCE FREQUENCY NOTATION.................... 1-5 3.1.1.2-1 RADIATION MONITORING INSTRUMENTATION............... 3/4 1-3 l 4.1.1.2-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS....................................... 3/4 1-6 3.1.1.3-1 SEISMIC MONITORING INSTRUMENTATION................ 3/4 1-8 l 4.1.1.3.1-1 SEISMIC M'ONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS......................... 3/4 1-9 3.1.1.4-1 METEOROLOGICAL MONITORING INSTRUMENTATION......... 3/4 1-11 4.1.1.4-1 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.......................... 3/4 1-12
<"% 3.2.1-1 L7MITING VALUES OF SETTLEMENTS OF REACTOR .
I s_) BUILDING (RB)...................................... 3/4 3-6 5.7.1-1 COMPONENT CYCLIC-OR TRANSIENT LIMITS............... 5-8 l
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I-I. , SECTION 1.0 s DEFINITIONS )
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I.0 DEFINITIONS Thb following terms are defined so that uniform interpretation of these cpecifications may be achieved. The defined terms appear in capitalized ;
type and shall be applicable throughout these Technical Specifications. [
i ACTION !
1.1 ACTION shall be that part of a Specification which prescribes remedial measures required under designated conditions. ;
-CHANNEL CALIBRATION
' 1. 2 A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such.that it responds with the necessary range and ;
accuracy to known values of the parameter which the channel monitors.
The CHANNEL CALIBRATION shall encompass the entire channel includina >
the sensor and alarm and/or trip functions, and shall include the ;
CHANNEL FUNCTIONAL TEST. The CHANNEL CALIBRATION may be performed by any. series of sequential, overlapping or total channel steps such that the entire channel is calibrated.
HANNEL CHECK
.3 A CHANNEL CHECK shall be the qualitative assessment of channel l
behavior during operation by observation. This determination shall include, where possible, comparison of the channel indication and/or i status with other indications and/or status derived from independent l
instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL EST 1.4 A CHANNEL FUNCTIONAL TEST shall be:
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a. Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify
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OPERABILITY including alarm and/or. trip functions and channel failure trips,
b. Bistable channels - the injection of simulated signal into the '
sensor to verify OPERABILITY includino alarm and/or trip functions.
The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is tested.
OSHOREHAM - UNIT 1 1-1
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DEFINITIONS FREQUENCY NOTATIONS 1.5 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.
MEMMER(S) OF THE PUBLIC 1.6 MEMBER (S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this cateaory are persons who enter the site to service equipment or to make deliveries. This catecory does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL (ODCM) .
l 1.7 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodolocy and parameters used in the calculation of offsite doses resultina from radioactive gaseous and liquid effluents, in the fs calculation of caseous and liquid effluent monitoring Alarm / Trip
-( Setpoints, and in the conduct of the Environmental Radiological i
Monitoring Procram. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radioloaical Environmental Monitoring Programs required by Section 6.7.4 and (2) descriptions of the information that
i. should be included in the Annual Radiological Environmental Operating ,
l. and Semiannual radioactive Effluent Release Reports required by Specifications 6.8.1.3 and 6.8.1.4.
OPERABLE - OPERABILITY 1.8 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified
! function (s) and when all necessary attendant instrumentation, controls, electrical power, coolina or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s) .
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' DEFINITIONS , , , , l PROCESS CONTROL PROGRAM i 1
1.9 _The PROCESS CONTROL PROGRAM (PCP) shall contain the current formulas, sampling, analyses, tests, and determinations to be made to ensure that processing and packaging of solid radioactive wastes based en demonstrated procescina of actual or simulated wet solid' wastes will be accomplished in such a way as to assure compliance with 10 CFR Parts 20, 61, and 71, State reculations, burial ground requirements, '
and other requirements governing the disposal of solid radioactive waste. .
1 REPORTABLE EVENT 1.10 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50. l SECONDARY CONTAINMENT INTEGRITY 1.11 SECONDARY CONTAINMENT INTEGRITY s!all exist whent
a. All secondary containment penetrations required to be closed
() during accident conditions are either:
1. Capable of being closed by an OPERABLE secondary containment automatic isolation system, or l l
2. Closed by at least one manual valve, blind flanae, or I I
deactivated automatic valve secured in its closed position, except as provided in Table 3.2.1.2-1 of Specification l 3.2.1.2.
Eb . All secondary containment hatches are closed and sealed,
c. At least one door in each access to the secondary containment is closed,
d. The sealing mechanism associated with each secondary containment ,
I penetration, e.a., welds, bellows, or 0-rings, is OPERABLE.
e. The pressure within the secondary containment is less than or equal to the value required by Specification 4.2.1.la.
SITE BOUNDARY 1.12 The SITE BOUNDARY shall be that line beyond which the land is neither
', owned, nor leased, nor otherwise controlled by the licensee.
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'r.C DEFINITIONS UNRESTRICTED AREA 1.13 An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of l protection of individuals from exposure to radiation and radioactive i i naterials, or.any area'within the SITE BOUNDARY used for residential l quarters or for industrial, commercial, institutional and/or I recreational purposes.
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DEFINITIONS TABLE 1.1 SURVEILLANCE' FREQUENCY NOTATION NOTATION FREQUENCY S At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
W' . At least once once per 7 days.
M At least once per 31 days.
L Q At least once per.92 days.
SA At least once per 184 days, l
A At least once per 366 days.
O' R At least once per 18 months (550 days)
N.A. Not applicable.
P Completed prior to each release.
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Sections 3.0 and 4.0 LIMITING CONDITIONS FOR FUEL HANDLING OPERATION AND
SURVEILLANCE REQUIREMENTS -l I
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3/4.0 APPLICABILITY LIMITING CONDITION FOR FUEL HANDLING OPERATION
i 3.0.1 Compliance with the Limiting Conditions for Fuel Handlino Operation ;
c:ntained in the succeeding Specifications is required durina the .
applicability conditions specified therein; except that upon failure to !
i mest the Limitina Conditions for Fuel Handling Operation, the associated ACTION requirements shall be met. ;
3.0.2 Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Fuel Handling Operation and associated ACTION rOguirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the cpecified time intervais, completion of the Action requirements is not i r0guired. ;
I 3.0.3 Commencement of fuel handlina operations shall not be made when the conditions for the Limiting Conditions for Fuel Handling Operation are not m3t and the associated ACTION requires suspension of fuel handling L op3 rations if they are not met within a specified time interval. Fuel '
h ndlina operations may be made in accordance with the ACTION requirements sn conformance to them permits continued operation of fuel handlina for unlimited period of time.
SURVEILLANCE REOUIREMENTS +
4.0.1 Surveillance Requirements shall be met durina applicability canditions specified for individual Limiting Conditions for Fuel Handling Oparation.
4.0.2 Each Surveillance Requirement shall be performed within the opacified surveillance interval with a maximum allowable extension not to cxceed 25% of the specified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed curveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Fuel Handlino Operation. The time limits of the ACTION requirements aro applicable at the time it is identified that a surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less then 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
-Surveillance requirements do not have to be performed on inoperable aquipment.
4 Commencement of fuel handlina operations shall not be made unless
(~).0.4 9 Surveillance Requirement (s) associated with the Limiting Conditions for k eu21 Handling Operation have been performed within the applicable surveillance interval or as otherwise specified.
SHOREHAM - UNIT 1 3/4 0-1
NSTRUMENTATION RADIATION MONITORING INSTRUMENTATION l
LIMITING CONDITION FOR FUEL HANDLING OPERATION l l
3.1.1.2 The radiation monitoring instrumentation channels shown in Table !
3.1.1.2-1 shall be OPERABLE with their alarm / trip setpoints within the cpecified limits.
APPLICABILITY: As shown in Table 3.1.1.2-1.
ACTION: !
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m. With an Area Monitor instrumentation channel alarm / trip setpoint exceeding the vclue shown in Table 3.1.1.2-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.
b. With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.1.1.2-1.
SURVEILLANCE REQUIREMENTS 4.1.1.2 Each of the above required radiation monitoring instrumentation chcnnels shall be demonstrated OPERABLE by the performance of the CHANNEL L CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the l
c nditions and at the frequencies shown in Table 4.1.1.2-1.
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s O _ TABLE 3.1.1.2-1 i
RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM MEASUREMENT INSTRUMENTATION OPERABLE CONDITION SETPOINT RANGE ACTION !
1. Area Monitors
a. Criticality .
Monitors :
1) New Fuel ~
Storage Vault 2**
f,20 mR/hr 10 1 to 10 4 mR/hr 1 3
2) Spent Puel 2**
4 20 mR/hr 10 1 to 10 mR/hr 1 Storage Pool i I
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TABLE 3.1.1.2-1 (Continued) l RADIATION MONITORING INSTRUMENTATION TABLE NOTATIONS l
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cWhenever fuel is in the Storage Vault or Spent Fuel Pool.
00These two areas are monitored by the same two detectors. l l
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TABLE _3.1.1.2-1 (Continued) i RADIATION MONITORING INSTRUMENTATION l
ACTION STATEMENT ACTION 1 - With the required monitor inoperable, assure a portable continuous monitor with the same alarm setpoint is OPERABLE in,the vicinity of the' installed monitor during any fuel movement. If no fuel movement ic being made, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
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. TABLE 4.1.1.2-1 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CONDITIONS )
y CHANNEL TOR WHICH ;
CHANNEL FUNCTIONAL CHANNEL SURVEILLANCE :
INSTRUMENTATION CHECK TEST CALIBRATION y RT.OUIRED 1 Area Monitors i
a. Criticality Monitors
1) New Fuel Storage S M R
i Vault
2) Spent Puel S M R
l Storage Pool l l
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0 -Whenever fuel is in the Storage Vault or Spent Fuel Pool. j l
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INSTRUMENTATION ;
l SEISMIC MONITORING INSTRUMCNTATION LIMITING CONDITION FOR FUEL HANDLING OPERATION i
3.1.1.3 The seismic monitoring instrumentation shown in Table 3.1.1.3-1 l ch311 be OPERABLE. l APPLICABILITY: At all times.
I ACTION: j
a. With one or more of the above required seismic monitoring !'
instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification i , 6.8.2 within the next 10 days outlinino the cause of the o malfunction and the plans for restoring the instrument (s) to ;
OPERABLE status. ]
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, j@pRVEILLANCE REQUIREMENTS I
l h,1.1.3.1 Each of the above required seismic monitoring instruments shall l M demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the frequencies Chown in Table 4.1.1.3.1-1, 4.1;1.3.2 Each of the above required seismic monitorino instruments cctuated during a seismic event greater than or equal to 0.01 o shall be rGstored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 5 days following the seismic event. Data shall be rctrieved from actuated instruments and analyzed to determine the maanitude of the vibratory ground motion. A Special Report shall be prepared and ,
cubmitted to the Commission pursuant to Specification 6.8.2 within 10 days doccribing the maanitude, frequency spectrum, and resultant effect upon
-ctction features important to safety. ;
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1 SEISMIC MONITORING INSTRUMENTATION
.-r. ,q MINIMUM i MEASUREMENT INSTRUMENTS l INSTRUMENTS AND SENSOR LOCATION RANGE OPERABLE 1.' Triaxial Time-History Accelerographs j
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c, a. Primary Containment Mat, outside 0.01-1 g 1 i and adjacent to primary I containment wall :
b. Outside Primary Containment Wall 0.01-1 g 1
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El 131'-7" ;
c. Free Field 0.01-1 g 1
2. Triaxial Seismic Switches l i
t. . Primary Containment Mat 0.01 g 1* ,
1 ). Triaxial Response-Spectrum Recorders 1 a,, Containment Mat El 8'-0" 0.01-2 g 11 *
' b.
Reactor Pedestal Wall - El'70'-8" 0.01-2 g 1 ,
i CWith reactor control room indication.
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TABLE 4.1.1.3.1-1 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL INSTRUMENT AND SENSOR LOCATIONS CHECK TEST CALIBRATION F
1.- Triaxial Time-History Accelerographs i 7
a. Primary Containment Mat, ,
outside and adjacent to !
primary containment wall M* SA R
b. Outside Primary Containment Wall - El 131'-7" M* SA R
c. . Free Field . M* SA R m 2 Triaxial Seismic Switches i I
a. Primary Containment Mat ** M SA R !
3. Triaxial Response-Spectrum Recorders .
l s u. Containment Mat El 8'-0"** M SA R
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b. Reactor Pedestal Wall ,
El 70'-8" I a,Except seismic triqqer ;
00 with reactor control room-indications i
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INSTRUMENTATION i r !
METEOROLOGICAL MONITORING INSTRUMENTATION i
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LlylTING CONDITION FOR FUEL HANDLING OPERATION 3.1.1.4 The meteorological monitoring instrumentation channels on the
. 400-ft-tower shown in Table 3.1.1.4-1 shall be OPERABLE. .
APPLICABILITY: At.all times. l ACTION: ,
With one or more meteorological monitoring instrumentation I a.
channels inoperable for more than 7 days, prepare and submit a
Special Report to the Commission pursuant to Specification 6.8.2 .
within the next 10 days outlining the cause of the malfunction ,
and the plans for restoring the instrumentation to OPERABLE
status.
SURVEILLANCE REQUIREMENTS l 1.1.4 Each of the above required meteorological monitoring
. natrumentation channels shall be demonstrated OPERABLE by the performance ,
of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies
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l chtwn in Table 4.1.1.4-1.
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c TABLE }.1.1.4-1 METEOROLOGICAL MONITORING INSTRUMENTATION r MINIMUM' .
INSTRUMENTS >
INSTRUMENT OPERABLE 1, Wind Speed '
i Elev. 33/150 ft 1 ,
. 2. WindLDirection Elev. 33/150 ft 1
'3. Air Temperature Difference ,
Elev. 33/150 ft 1 h
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TABLE 4.1.1.4-1 !
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L METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS l
' CHANNEL CHANNEL 6 INSTRUMENT CHECK CALIBRATION
-1 Wind Speed Elev. 33/150 ft D SA 2 Wind Direction
'Elev. 33/150 ft D SA
'3 Air Temperature Difference Elev. 33/150 ft D SA t
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3/4.2 CONTAINMENT SYSTEMS f 3/4.2.1 SECONDARY CONTAINMENT l SECONDARY CONTAINMENT INTEGRITY LIMITING CONDITION FOR FUEL HANDLING OPERATION t
3.2.1.1 SECONDARY CONTAINMENT INTEGRITY shall be maintained. ,
APPLICABILITY: When irradiated fuel is being handled in the secondary containment.
. ACTION: .
Without SECONDARY CONTAINMENT INTEGRITY, suspend handlino of '
irradiated fuel in the secondary containment.
SURVEILLANCE REQUIREMENTS .
l 4.2.1.1 SECONDARY CONTAINMENT INTEGRITY shall be demonstrated by:
() a. Verify at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the pressure within the secondary containment is less than or equal to 1.0 inch of vacubm '
water gauge.
b. Verifying at least once per 31 days that:
1. All secondary containment equipment hatches are closed and sealed.
2. At least one door in each access to the secondary containment is closed except for routine entry and exit.
3. All secondary containment penetrations not capable of being ,
closed by OPERABLE secondary containment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flances, or deactivated automatic valves secured in position.
OSHOREHAM - UNIT 1 3/4 2-1
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3/4.3' PLANT SYSTEMS 3/4.3.1 SEALED SOURCE CONTAMINATION .
LIMITING CONDITION FOR FUEL HANDLING OPERATION 3.3.1 Each sealed source containing radioactive material either in excess of-100 microcuries of beta and/or camma emitting material or 5 microcuries of alpha emitting material shall be free of greater than or equal to 0.005 -
microcurie of removable contamination.
APPLICABILITY: At all times.
ACTION: , ,
With a sealed source havino removable contamination in excess of the above limit, withdraw the sealed source from use and either:
1. Decontaminate and repair the sealed source, or .
2. Dispose of the sealed source in accordance with Commission Reculations. ,
bRVEILLANCEREQUIREMENTS 4.3.1.1 Test Requirements - Each sealed source shall be tested for leakace and/or contamination by:
a. The licensee, or
b. Other persons specifically authorized by the Commission or an Agreement State.
Tha test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.
4.3.1.2 Test Frequencies - Each category of sealed sources, excluding ctortup Fources and fission detectors previously subjected to core flux, chs11 be tested at the frequency described below,
a. Sources in use - At least once per six months for all sealed sources containino radioactive material:
1. With a half-life greater than 30 days, excluding Hydrocen 3, and
2. In any form cther than gas.
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PLANT SYSTEMS SURVEILLANCE REQUIREMENTS'(Continued) ,
b.- Stored sources not in use - Each sealed source and fission detector shall be tested prior to use or transfer to another licensee unless tested within the previous 6 months. Sealed sources and fission detectors transferred without a certificate
+ . indicating the last test date shall be tested prior to being placed into use.
c. _Startup sources and fission detectors - Each sealed startup source and fission detector shall be tested within 31 days following repair or maintenance to the source.
4.3.1.3 Reports _A report shall be prepared and submitted to the
- Commission on an annual basis if sealed source or fission detector leakaue-
tests reveal the presence of creater than or equal to 0.005 microcurie of
removable contamination.
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l LANT SYSTEMS
-3/4.3.2 SETTLEMENT OF REACTOR BUILDING TOTAL-SETTLEMENT L LIMITING CONDITION FOR PUEL HANDLING OPERATION l
L 3.3.2.1: -The total settlement of the Reactor Building shall not exceed 4.0 l inches (80% of the limiting value specified in Table 3.3.2.1-1).
l APPLICABILITY: At all times.-
ACTION:
1 With the total settlemen't of the Reactor Building reaching 4.0 inches (80%
'of the limiting ~ settlement value specified in Table 3.3.2.1-1), conduct an L Ongineering review,of field conditions and evaluate the-consequetices of
l ddditional settlement. Submit a Special Report to the Commission pursuant to' Specification 6.8.2 within 30 days, containing the results of the investigation, the evaluation of existing and possible continued cattlement, and the remedial action to be taken, if any, including the date of the next survey, 1; ,
's.eURVEILLANCES REQUIREMENTS 4.3.2.1 'The total settlement of the Reactor Building shall be determined to=the nearest 0.01 foot by measurement and calculation:
l a.- At least once every 6 months i l
1. Until observed settlement has stabilized *, and
2. Whenever previously stabilized
settlement exceeds 0.10 inch L
since.the previous reading.
! 4 l b. At least once every 24 months thereafter. l 1
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0.10 inch from previous reading.
MOREHAM - UNIT 1 3/4 3-3 I l l
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m LANT-SYSTEMS
' DIFFERENTIAL' SETTLEMENT ACROSS THE STRUCTURE LIMITING CONDITION FOR FUEL ~ HANDLING OPERATION 3.3.2.2- The differential settlement across the Reactor Building shall not Gxceed 1.6. inches (80% of the limiting value specified in Table 3.3.2.1-1) .
APPLICABILITY At all times.
ACTION:
With the differential settlement across the Reactor Building exceeding 1.6~
inches.(80% of the allowable. settlement valueEspecified in Table 3.3.2.1-1), conduct an e'naineering review of field conditions and evaluate tho-consequences of additional settlement. Submit a Special Report to the Commission pursuant to Specification 6.8.2 within 30 days, containing the -
racults of the investigation, the evaluation of existino and possible continued settlement, and the remedial action to be taken, if any, including the date of the next survey.
~~1RVEILLANCE REQUIREMENTS 4.3.2.2 The differential settlement across the Reactor Building shall be dstermined to the nearest 0.01 foot by measurement and calculation:
a. At least every 6 months Until observed settlement has stabilized *, and !
1.
2. Whenever previously stabilized
settlement exceeds 0.10 inch since the previous reading.
b. 'At least once every 24 months thereafter.
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0.10 inch from previous reading.
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([VHOREHAM - UNIT 1 3/4 3-4 l-L L
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LANT' SYSTEMS PENETRATION DIFFERENTIAL SETTLEMENT - STRUCTURE TO SOIL LIMITING-CONDITION FOR FUEL HANDLING OPERATION 3o3.2.3 The penetration-differential settlement - structure to soil shall-not exceed'O.70 inch (80% of the limiting value specified in Table 3.3.2.1-1).
-APPLICABILITY: At all times.
ACTION:.
With-.the penetration differential settlement - structure to soil exceeding 0.70. inch (80% of the allowable settlement value specified in Table 3.3.2.1-1), conduct an enoineering review of field conditions and evaluate theLconsequences of additional settlement. Submit a Special Report to the Commission pursuant to Specification 6.8.2 within 30 days, containing the results of the investigation, the evaluation of existing and possible continued-settlement, and the remedial action to be taken, if any, including the date of the next survey.
URVEILLANCE REQUIREMENTS
'4o3.2.3 The penetration differential settlement - structure to soil shall bn determined to the-nearest 0.01 foot by measurement and calculation.
a. At'least once every 6 months.
1. Until observed settlement has stabilized *, and
2. Whenever previously stabilized
settlement exceeds 0.10 inch since the previous readina.
b. At least once every 24 months thereafter.
0.10 inch from previous readino.
OREHAM - UNIT 1 3/4 3-5
-n TABLE 3.3.2.l ' LIMITING VALUES OF SETTLEMENTS OF REACTOR BUILDING (RB) '
I LIMITING VALUE' SETTLEMENT: (inches) 1 Total absolute settlement 5.0 1
2 , Differential settlement across L. RB (Tilt) 2.0 ,
L 3 Penetration; differential settlement (between' structure to soil for differential settlement of i buried' pipes) 0.9 1 l
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SHOREHAM - UNIT 1 3/4 3-6
3 ELECTRICAL POWER SYSTEMS
/4.4.
3/4.4.1 A.C. SOURCES LIMITI'NG CONDITION FOR FUEL HANDLING OPERATION p
3.4.1 One. circuit.between the offsite transmission network and the onsite l diotribution system shall be OPERABLE.
L, APPLICABILITY: When handling-irradiated fuel in the secondary containment.
ACTION:.
With the offsite circuit A.C. electrical power source inoperable suspend 1
handling of. irradiated fuel in the secondary containment and crane .
op3 rations over the spen't~ fuel storage pool when fuel assemblies are stored thcrein. 1 SURVEILLANCE REQUIREMENTS ;
I g 4.4.1 The above required independent circuit between the offsite l l transmission network and the onsite Class lE distribution system shall be L /'"ptermined OPERABLE at least once per 7 days by verifyinc correct breaker L (._slignments and indicated power availability.
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, x-ELECTRICAL' POWER ~ SYSTEMS-
?3/4.4.2- ONSITE POWER DISTRIBUTION SYSTEMS LIMITING CONDITION FOR FUEL HANDLING OPERATION ,, .!
'y 3.4.2 As.a minimum,-two of the following A.C. power distribution system divisions:shall be energized:
a.. A.C. power distributions.
1. Division 1 consisting of:
a) 4160-volt A.C. bus 101.
b) 480-volt A.C. bus 111 and MCCs 1110 through 1119, 111W, 111Y and 1112.
c) 120-volt A.C. distribution panels-R1, R2, and R3.
2. Division 2 consisting of:
1' i
a) 4160-volt A.C. bus 102 b) 480-volt A.C. bus 112 and MCCs 1120 through 1129, 112W and 112X.
j(sf c) 120-volt A.C. distribution panels in B1, B2 and B3. I
3. Division 3 consisting of: ;
a) .4160-volt A'.C. bus 103 -
b) 480-volt A.C. bus 113 and MCCs 1131, 1133 and 1134. .
c) 120-volt A.C. distribution panels 01 and 02. l 1
APPLICABILI7T -When handling irradiated fuel in the secondary containment
ACTION

1 L With two divisions of the above required A.C. divisions not energized, suspend handling of irradiated fuel in the secondary containment..
i SURVEILLANCE REQUIREMENTS L 4.4.'2 'At least the above required power distribution system divisions shall be determined energized at least once per 7 days by verifying correct i l- breaker alignment and voltage on the busses and power availability to the .1 l MCCs and the panels. l l
O SHOREHAM - UNIT 1 3/4 4-2
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$2[4.5 FUEL HANDLING OPERATIONS 3/4.5.1' COMMUNICATIONS
_E LIMITING CONDITION FOR FUEL HANDLING OPERATION !
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, 3.5.1: Direct communication-shall be maintained between the control room Cnd refuelina platform personnel, iAPPLICABILITY: Whenever handling irradiated fuel.
ACTION t :
1 Wh3n direct communication between the control room and refueling platform personnel cannot be maintained, immediately suspend handling of irradiated fu21. .
b.
SURVEILLANCE REQUIREMENTS-L
.5.1 Direct communication between the control room and refueling platform rsonnel shall' be demonstrated within one hour prior to the start of and-
.at-least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during handling of irradiated fuel.
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FUEL HANDLING-OPERATIONS-3/4.5.2 REFUELING PLATFORM LIMITING CONDITION FOR FUEL HANDLING OPERATION -
3. 5. 2 - The refueling platform shall be OPERABLE and used forEhandling fuel
.ossemblies or. control rods.
-APPLICABILITY: During handling of fuel assemblies or control rods.
ACTION:
'With the requirements for refueling platform OPERABILITY not satisfied,
'ouspend use of any inope'rable refueling platform equipment from operations involving the handling of control rods and fuel assemblies after placing the load in a-safe condition.
'_ SURVEILLANCE REQUIREMENTS
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4.5.2 Each'refuelino platform crane or hoist used for handlino of control 1
ds or fuel assemblies shall be demonstrated OPERABLE within 7-days prior the start of such operations with that crane or hoist by
a. Demonstrating operation of the overload cutoff on the main hoist-when the load exceeds 1200 1 50 pounds..
.* b. Demonstrating operation of the overload cutoff on the frame mounted and monorail hoists when the load exceeds 1000 1 50 pounds,
c. Demonstrating the operation of the_uptravel mechanical cutoff on the frame mounted monorail hoists when uptravel brings the top of active fuel assembly to 7 feet below the normal fuel storage pool water level.
d. Demonstrating operation of the slack cable cutoff on the main hoist when the load is less than 50 1 25 pounds.
SHOREHAM - UNIT 1 3/4 5-2 0
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e. Demonstrating operation of the loaded interlock on the main hoist
.when the load exceeda. 485 1 50-pounds.
.[; ' f . Demonstrating' operation of the loaded interlock on the auxiliary
~ hoist;when the load exceeds 400 1 50 pounds.
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HOREHAM - UNIT 1 3/4 5-3
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'O FUEL ~ HANDLING OPERATIONS y.
-3/4.5.3 CRANE TRAVEL LIMITING CONDITION FOR FUEL HANDLING OPERATION 3.5.3 Loads in: excess of 1200 pounds shall be prohibited from travel over ths spent fuel storage pool racks with fuel assemblies in the spent fuel ;
otorage pool racks and the spent fuel shipping cask movement shall be prchibited from travel over the refueling floor except when moved by the ,
OPERABLE polar crane.
APPLICABILITY: At all times.
ACTIONt' ,
With the requirenaents of the above specification not satisfied, place the crane load in'a safe condition.
' SURVEILLANCE REQUIREMENTS 5.3 The polar crane shall be demonstrated OPERABLE:
a. Within 7 days prior to and at least once per 7 days durina movement of loads in excess of 1200 pounds over the spent fuel L storage pool racks or movement of the spent fuel shipping cask L over the-refueling floor by:
1. Verifying the redundancy of the crane brakes, cear trains, reeving system, and load attaching points by visual inspection.
2. Demonstrating OPERABILITY of the crane interlocks, limit switches, alarms and fail safe control components by functional test. ,
3. Performance of a wire rope inspection in accordance with ANSI B30.2, 1976.
b. By performance of a wire rope inspection in accordance with ANSI B30.2, 1976. The wire rope shall be replaced should any of the replacement criteria of ANSI B30.2 be met.
I O SHOREHAM - UNIT 1 3/4 5-4
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' FUEL HANDLING OPERATIONS-
3/4.5.4 WATER LEVEL - SPENT FUEL STORAGE POOL LIMITING CONDITION FOR FUEL HANDLING OPERATION 3.5.4 At least 21' feet of water shall be maintained over the top of irradiated fuel assemblies seated in the spent fuel storage pool racks.
APPLICABILITY: At all times.
ACTION:
With the requirements of the above specification not satisfied, suspend all
-movement of fuel assemblies and crane operations with loads in the spent
-fuel storage pool area after placing the fuel assemblies and-crane load in
-a safe condition. Restore level.
SURVEILLANCE REQUIREMENTS 4.5.4 The water level in the spent fuel storage pool shall be determined be at least at its minimum required depth at least once per 7 days.
OSHOREHAM - UNIT 1 3/4 5-5
j ir-4
's BASES'FOR SECTIONS 3.0 AND 4.0 LIMITING CpNDITIONS FOR FUEL HANDLING OPERATION AND SURVEILLANCE REQUIREMENTS O
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1 NOTE The BASES contained in succeeding pages summarize .
the reasons for the Specifications in Section 3.0 and 4.0, but in accordance with 10 CFR 50.36 are not part of these Technical Specification.
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3/4.0 APPLICABILITY BASES The specifications of this section provide the general requirements cpplicable to each of the Limiting Conditions for Operation and Surveillance Requirements within Section 3/4.
3.0.1 This section states the applicabliity of each specification in tsrms of the specified condition and is provided to delineate specifically whsn each specification is applicable.
The ACTION requirements establish those. remedial measures that must be tchen within specified time limits when the requirements of a Limitina condition for Operation are not met. The specified time limits of the u ACTION requirements are applicable from the point in time there was a i failure to meet a Limiting Condition for Operation. The time limits of the
. ACTION requirements are also applicable when a system or component is L removed from service for surveillance testing or investigation of op0 rational problems. Individual specifications may include a specified time limit for the. completion of a Surveillance Requirement when equipment is removed from service. In this case, the allowable outage time limits of g -Vh@ ACTION requirements are applicable when this limit expires if the s ,hrveillance has not been completed.
Compliance with ACTION requirements that permit continued operations of fuel handlina for an unlimited period of time provides an acceptable lovel of safety for continued operation without regard to the status of the plant before or after fuel handling operations. Therefore, in this case fus1 handlina operations may be made in accordance with the provisions of tha' ACTION requirements. The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before starting operations of fuel handling.
3.0.2 This specification defines those conditions necessary to constitute compliance with the terms of an individual Limiting Condition l for Operation and associated ACTION requirement.
3.0.3 This specification provides that commencement of fuel handling opsrations must be made with the full complement of required systems, equipment or components OPERABLE per the requirements of the Limiting Conditions for Operation.
The intent of this provision is to ensure that handlina of irradiated fuel is not initiated with either required equipment or systems inoperable or other limits being exceeded.
B 3/4 0-1 C-)10REHAM-UNIT 1
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t I P_PLICABILITY DASES 4.0.1 This specification provides that surveillance activities nOcessary to ensure the Limiting _ Conditions for Operation are met and will ba performed during the conditions for which the Limiting Conditions for
.Oparation are applicable. Provisions for additional surycillance activities te be performed without rsgard to the applicable conditions are provided in the individual Surveillance Requirements.
4.0.2 The provisions of this specification provide allowable
. tolerances for performing surveillance activities beyond those specified in eths nominal surveillance interval. These tolerances are necessary to provide operational flexibility because of scheduling and performance considerations.. The' phrase "at least" associated with a surveillance >
fr0guency does not negate this allowable tolerance; instead, it permits the more frequent performance of surveillance activities.
4.0.3 The provisions of this specification' set forth the criteria for determination of compliance with the OPERABILITY requirements of the Limiting conditions for Operation. Under this criteria, equipment, systems p . 'or components are assumed to be OPERABLE if the associated surveillance l
rstivities have been satisfactorily performed within the specified time L (_ hterval. Nothing in this provision is to be construed as defining
i. ' cquipment, systems or components OPERABLE, when such items are found or known to be inoperable although still meeting the Surveillance R3quirements.
This specification also clarifies that the ACTION requirements are
[.c
applicable when Surveillance Requirements have not been completed within
-ths allowed surveillance interval and that the time limits of the ACTION l- requirements apply from the point the time it is identified that a l surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Rsquirement within the allowable outage time limits of the ACTION i
rsquirements restores compliance with the requirements of Specification i
4.0.3. However, this does not negate the fact that the failure to have parformed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action. Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 and not meetina the associated ACTION requirements per Specification 3.0.1 is a violation of Technical Specification requirements and is, therefore, a reportable event under the requirements of 10 CFR 50.73 (a) (2) (1) (B) because it is a condition prohibited by the plant's Technical Specifications.
SHOREHAM - UNIT 1 B 3/4 0-2
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1 APPLICABILITY BASES-
)
If the allowable outage time limits of the ACTION requirements are 1 sos than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , a 24-hour-allowance is provided to permit a delay in implementing the ACTION requirements. This provides an adequate time limit to complete Surveillance Requirements that have not been performed. The purpose of this allowance is to permit the completion of a surveillance i
-before a suspension of fuel handling would be required to comply with ACTION requirements or before other remedial measures would be required that may preclude the completion of a surveillance. The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required -to perform the surveillance, and the safety significance of the delay in completing the required j ourveillance. If a surveillance is not completed within the 24-hour L cllowance,.the time limits of the ACTION requirements are applicable at'
~ that time. When a surveillance is performed within the 24-hour allowance l and the Surveillance Requirements are not met, the time limits of the l- ACTION requirements are applicable at the time the surveillance is I
tGrminated.
Surveillance Requirements do not have to be performed on inoperable uipment because the ACTION requirements define the' remedial measures that pply. However, the Surveillance Requirements have to be met to' dsmonstrate that' inoperable equipment has been restored to OPERABLE status.
4.0.4 This specification ensures that surveillance activities associated with Limiting Conditions for Operation for handling irradiated fuel have been performed within the specified time interval prior to handling irradiated fuel. The intent of this provision is to ensure that surveillance activities.have been satisfactorily demonstrated on a current basis as required to' meet the OPERABILITY requirements of the Limiting' Condition for Operation. -
i V IOREHAM - UNIT 1 B 3/4 0-3
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'b J- j 3/4.1 INSTRUMENTATION BASES 3/4.1.1 MONITORING INSTRUMENTATION 3/4.1.1.1 RADIATION MONITORING INSTRUMENTATION L The OPERABILITY of the radiation monitoring instrumentation ensures
_ th:t (1) the radiation levels are continually measured in the areas acrved by the individual channels; (2) the alarm or automatic-action is initiated when the radiation level trip setpoint is exceeded; and (3) cufficient information is available on selected parameters to monitor and oscess these variables following an accident.- This capability is consistent with 10 CFR P' art 20, 10 CFR Part 50, Appendix A, General Design l' . Criteria- 19,-41, 60, 61, 63 and 64.
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(. 3/4.1.1.2 SEISMIC MONITORING INSTRUMENTATION L
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'The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a
'anismic event and evaluate the response of those features important to ,
f- afety. .This capability is required to permit comparison of the measured '
\s,)sponse to that used in the design-basis for the station. This instrumentation is consistent with the recommendations of Regulatory Guide 1.12 " Instrumentation for Earthquakes", April 1974.
3/4.1.1.3 METEOROLOGICAL MONITORING INSTRUMENTATION L
The OPERABILITY of the meteorological monitoring instrumentation
' ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. The capability is required to evaluate the need for initiating protective mansures to protect the health and safety of the public. This instrumentation is consistent with the recommendations of Reaulatory Guide 1.23 "Onsite Meteorological Programs," February 1972.
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/4.2 CONTAINMENT SYSTEMS-BASES J 3/4.2.1 SECONDARh CONTAINMENT Secondary containmen't is designed to minimize and monitor any cround lovel' release of~ radioactive material which may result from an accident.
Wh n handling irradiated fuel in the secondary containment, secondary- ,
c ntainment integrity is required.
.. Establishing and maintaining a vacuum in the reactor building, along .
with the surveillance of the doors, hatches, dampers and valves, is cd quate to ensure'that there are no violations of the integrity of the >
cscondary containment. ,
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3/4.3 PLANT SYSTEMS
[ BASES 3/4.3.1 SEALED SOURCE CONTAMINATION 2' .The-limitations on removable contamination for sourcec requiring leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakaae from byproduct, b source, and.special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the
_ probability of damage to a source in that group. Those sources which are
= frequently handled are required to be tested more often than those which are not. Sealed sources'which are continuously enclosed within a shielded mechanism, i.e., sealed sources within radiation monitorina devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.
[ 3/4.3.2 SETTLEMENT OF REACTOR BUILDING Total settlement of the Reactor Building can be used as an indicator E at confirms the adequacy of the underlying soils with respect to quefaction. Liquefaction of these soils is considered unlikely if the EE relative density exceeds 65%. Therefore, measured settlements that are E- less1than predicted, assuming the relative density of the underlyina soils EF equals 65%, confirm that the underlyino soils are sufficiently dense so as
to preclude liquefaction during the DBE.
Differential settlement across the Reactor Building would increase
~1oads on piping connected to the building due to anchor point rotation.
The requirements for measuring differential settlement across the building ensures that ample opportunity for further investigation and corrective
=_ action is provided if differential settlement approaches the allowable
- value.
Differential settlement between the Reactor Building and the soil
- would increase loads on the buried pipes that are connected to the t_
structure. The requirement for measuring settlement of the Reactor Building ensures that ample opportunity for further investiaation and corrective action is provided if differential settlement between the structure and the soil approaches the allowable value.
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_ SHOREHAM - UNIT 1 B 3/4 3-1
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J/4.4 ELECTRICAL POWER SYSTEMS
BASES 3/4.4.1 AND 3/4.4.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SYSTEMS i
The OPERAPILITY of the specified A.C. power source and associated dictribution systems during fuel storage ensures that sufficient Linotrumentation'and control capability is available for. monitoring and raaintaining the unit status.
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_/4.5 FUEL HANDLING OPERATIONS
t' BASES 3/4.5.1 COMMUNICATIONS ,
The requirement for communications capability ensures that refuelina Ct$ tion personnel can be promptly informed of significant changes in the ,
facility. status.
3/4.5.2 REFUELING PLATFORM The OPERABILITY requirements ensure that (1) the refuelina platform will be used for handling control rods and fuel assemblies, (2) each-crane and hoist has sufficient load capacity for handling fuel assemblies and control rods, and (3)-the core internals and pressure vessel are protected L from excessive lifting force in the event they are inadvertently engaged
! during lifting operations.
l l- 3/4.5.3 CRANE TRAVEL l
The restriction on movement of loads in excess of the nominal weight f a fuel assembly over other fuel assemblies in the storage pool and of a-spent fuel shipping cask over the refueling floor ensures that in the ont the load is. dropped (1) the activity release will'be limited to that contained in a single fuel assembly, (2) any possible distortion of fuel in tha storage racks will not result in a critical array, and (3) the redundancy of components assures the placement of the load in a safe condition. -This assumption is consistent with the activity release assumed-in the safety analyses.
3/4.5.4 WATER LEVEL - SPENT FUEL STORAGE POOL
-The restrictions on minimum water level ensure that sufficient water dapth is available to provide adequate shielding for the low burnup condition of the irradiated fuel assemblies. The minimum water depth is consistent with the. assumptions of the safety analysis.
OSHOREHAM - UNIT 1 B 3/4 5-1
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SECTION 5.0 1
DESIGN FEATURES
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SECTION 6.0 ADMINISTRATIVE CONTROLS-
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I N] 6.0 ADMINISTRATIVE CONTROLS i
o6.1 RESPONSIBILITY-16 . 1 . 11 The Plant Manager shall be responsible for overall unit operation ;
cndfahall delegate in writina the succession to this responsibility durina ,
.hiO absence. !
6,1.2 The. operator on shift shall be responsible for the plant
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- 6.2' ORGANIZATION T
6.2.1 -Nuclear Oraanization
. An organization shall be established for unit operation and-corporate menagement. This organization shall include the positions for activities
cffecting the safety of the nuclear plant.
a. Lines of authority, responsibility and communication shall be established and defined from the highest management levels through intermediate levels to and including all operating
organizations positions. These relationships shall be. documented and updated, as appropriate, in the form of organizational' charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the SAR and updated in accordance with 10 CFR 50.71(e) .
b. The responsible-Vice President shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
c. The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.
d. The individuals who train the operating staff and those who carry out health phys'ics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
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-ADMINISTRATIVE CONTROLS 1
UNIT STAFF 6.2.2 The station organization shall be subject to the following:
a. Each duty shift shall be composed of at least the minimum shift crew consisting of.three operators,
b. At'least'one operator who is qualified and capable of responding to any alarms that may occur should normally be in the Control Room when fuel is in the Spent Fuel Pool. However, he may leave the Control Room for brief periods of time.
c. - All fuel handl'ina operations shall be-observed and directly supervised by a licensed operator or individual licensed to supervise.the handlina of irradiated fuel, and who has no other concurrent responsibilities during this operation; and
d. Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work a normal 8-hour day, 40-hour week. However, in the event that unforeseen problems require substantial amounts of i ~
overtime to be used, or during extended periods of fuel movement, major maintenance, or major unit modification, on a temporary basis the following guidelines shall be followed:
l' l 1. An individual should not be permitted to work more than 16 l- hours straight, excluding shift turnover time.
2. An individual should not be permitted to work more than 16 L hours in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7-day period, l all excluding shift turnover time.
3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time.
Any deviation from the above guidlines shall be authorized by the Plant Manager or his deputy, or higher levels of management.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of the programs and procedures as outlined in Section 13 -
Conduct of Operations, of the Defueled Safety Analysis Report for comparable positions.
SHOREHAM - UNIT 1 6-2
=
= ADMINISTRATIVE CONTROLS
6.4 TRAINING 6.4.1 A retrainina and replacement trainina program for the station staff chall be maintained under the direction of the Training Supervisor, shall
-m20t'or exceed the requirements of the procrams and procedures as outlined iin Section 13.2 - Training Program, of the Defueled Safety Analysis Report.
6.5 ^ REVIEW AND AUDIT
'6:5.1 REVIEW OF OPERATIONS COMMITTEE (ROC) 4 FUNCTION
l 6.5.1.1- The ROC shall function to advise the Plant Manaaer on all matters related to nuclear safety.
COMPOSITION i
I 6.5.1.2 The ROC shall be composed of a chairman or ulternate chairman and our members or alternate members of the Plant Staff as desianated by the Eirman.
ALTERNATES -
6.5.1.3 All alternate members shall be appointed in writing by the ROC !
Chairman; however, no more than one alternate shall participate as a voting mrmber in ROC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The ROC shall meet at least once per calendar month and as convened by-the ROC Chairman or his designated alternato.
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-Q SHOREHAM - UNIT 1 6-3
i i
i MINISTRATIVE CONTROLS ,,
O'!ORUM 6.5.1.5 The quorum of the ROC necessary for the performance of the ROC i rCaponsibility and authority provisions of these Technical Specifications -
sh2ll consist of the Chairman or hls designated alternate and two other membirs including alternates.
I REDPONSIBILITIES, 6.5.1.6 The ROC shall be responsible for: I
a. Review of (1) all proposed procedures required by Specification }
6.7 and changes thereto, (2) all proposed programs required by Specification 6.7 and changes thereto, and (3) any other proposed '
procedures or chances thereto as determined by the Plant Manager to affect nuclear safety;
b. Review of all proposed tests and experiments that affect nuclear ;
safety; ,
c. Review of all proposed changes to Appendix A Technical Specifications;
}
d. Review of all proposed changes or modifications to unit systems t or equipment that affect nuclear safety;
e. Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the responsible Vice President; l f. Review of all REPORTABLE EVENTS;
q. Review of station operations to detect potential hazards to nuclear safety;
h. Performance of special reviews, investications, or analyses and i o reports thereon as requested by the Plant Manaaer;
i. Review of the Security Plan and implementino procedures;
j. Review of the Emergency Plan and implementing procedures; ,
k. Review of the Fire Protection Plan and implementing procedures; l
L O
SHOREHAM - UNIT 1 6-4
MINISTRATIVE CONTROLS
1. Review of the proposed changes to the Process Control Program (PCP);
m. Review of the proposed changes to the Offsite Dose calculation Manual (ODQ4);
n. Review of the proposed Major Changes to Radioactive Waste Systems;
o. Review of Personnel Radiation Records annually to determine how exposures might be lowered consistent with ALARA principles.
Document such considerations; and
p. Review of any accidental, unplanned, or uncontrolled radioactive release including the preparation of reports covering evaluation, recommendations, and disposition of the corrective action to prevent recurrence and the forwarding of these reports to the responsible Vice President.
6.5.1.7 The ROC shall:
( a. Recommend in writing to the Plant Manager approval or disapproval l f~}
ss of items considered under Specification 6.5.1.6a. through d. and l n. prior to their implementation.
b. Render determinations in writing with regard to whether or not each item considered under specification 6.5.1.6a. throuah e.
above constitutes an unreviewed safety question.
c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the responsible Vice President of disagreement between the ROC and the Plant Manacert however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
RECORDS i 6.5.1.8 The ROC shall maintain written minutes of each ROC meetinq that, I ct a minimum, document the results of all ROC activities performed under ,
ths responsibility provisions of these Technical Specifications. Copies chall be provided to the responsible Vice President.
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l SHOREHAM - UNIT 1 6-5
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i
.q MINI'STRATIVE CONTROLS 6.9.2 NUCLEAR REVIEW BOARD (NRB),
. FUNCTION 6.5.2.1 The NRB shall function to provide independent review and audit of docignated activities in the areas of:
a. Nuclear engineerinc,
b. Chemistry and radiochemistry,
c. Radioloaical safety, -
d. Mechanical and electrical engineering, and ;
e. Quality assura,nce practices. ,
Th3.NRU shall report to and advise the Assistant Vice President - Nuclear l Operations on those areas of responsibility in Specifications 6.5.2.7 and 6,5.2.8.
COMPOSITION 6.5.2.2 The NRB 'shall be composed of the permanent NRB Chairman and a i nimum of four permanent NRB members. The chairman and all members of the !
B shall have qualifications that meet the requirements of Section 4.7 of NSI/ANS 3.1-1978.
I Tha. membership shall include at least one individual from outside LILCO's er its contractors' organizations and at least one individual with substan-tic 1. nuclear experience. The nuclear experience may be provided by the individual who is from outside LILCO's or its contractors' organizations.
[
A_LTERNATES 6.5.2.3 All alternate members shall be appointed in writina by the NRB Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NRB activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NRB.
MEETING FREQUENCY L 6.5.2.5 The NRB shall meet at least once per six months.
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i SHOREHAM - UNIT 1 6-6 1-______________________ - - . - . . . . . -
i INISTRATIVE CONTROLS r
_OOORUM 6.5.2.6 The quorum of the NRB necessary for the performance of the NRB r0 View and audit functions of these Technical Specifications shall consist Cf the Chairman or his desionated alternate and at least three but not less th;n one-half of the NRB members present including alternates. No more th n a minority of the quorum shall have line responsibility for operation of the unit.
REVIEW {
6.5.2.'/ The NRB shall reviews
a. The safety evaluations for (1) changes to equipment or systems and (2) tests or experiments completed under the provision of 10 CFR 50.50 to verify that such actions did not consititute an unreviewed safety question;
b. Proposed chances to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; ,
r c. Proposed tests or experiments which involve an unreviewed safety i
4 question as defined in 10 CFR 50.59;
d. Proposed changes to Technical Specifications or this operatinc License; ,
l e. Violations of codes, regulations, orders, Technical t Specifications, license requirements, or of internal procedures or instructions havino nuclear safety sionificance;
f. Sionificant deviations from normal and expected performance of station equipment that affect nuclear safety;
g. All REPORTABLE EVENTS;
h. All recoonized indications of an unanticipated deficiency in nome ,
aspect of design or operations of structures, systems, or components that could affect nuclear safety; and
-1. Reports and meetino minutes of the ROC.
AUDITS l 6.5.2.8 Audits of station activities shall be performed under the l
cognizance of the NRB. These audits shall encompass:
O a. The conformance of station operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; SHOREliAM - UNIT 1 6-7
MINISTRATIVE CONTROLS ,
AUDITS (Continued)
b. The performance, training and qualifications of the entire staff at least once per 12 months;
c. The results of actions taken to correct deficiencies occurrina in unit equipment, structures, systems, or method of operation that affect nrelear safety, at least once per year; ,
d. The perfornvice of setivities required by the Quality Assurance Prcertm to reet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months; ,
e. The fire protection programmatic controls includino the implementing procedures, equipment and procram implementation at least once per 24 months utilizing either a cualified offsite licensee fire protection enaineer(s) or an outside independent fire protection consultant.
f. Any other area of station operation considered appropriate by the NRB, President or the Assistant Vice President - Nuclear Operations;
c. The radiolooical environmental monitorina procram and the results '
thereof al least once per 12 months;
. h. The OFFSITE DOSE CALCULATION MANUAL and implementiny procedurer at least once per 24 months; and
i. The PROCESS CONTROL PROGRAM and implementino procedures for solidifications of radioactive vastes at least once per 24 months.
j. The performance of activities required by the Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.
RECORDS 6.5.2.9 Records of NRB activities shall be prepared, approved, and
. distributed as indicated belows
a. Minutes of each NRB meeting shall be prepared, approved, and forwarded to the President and the Assistant Vice President -
Nuclear Operations within 14 days following each meetina.
,_s b. Reports of reviews encompassed by Specification 6.5.2.7 shall be e prepared, approved, and forwarded to the President and the Assistant Vice President - Nuclear Operations within 14 days followina completion of the review.
SHOPEHAM - UNIT 1 6-8
I .
j 9DMINISTRATIVECONTROLS RECO3DS (Continued) i
c. Audit reports encompassed by Specification 6.5.2.8 shall be i forwarded to the President, Assistant Vice President - Nuclear Operations and to the management positions responsible for the areas audited within 30 days after completion of the audit by the l auditing organization.
I 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a. The commission.shall be notified and a report submitted pursuant I to the requirements of Section 50.73 to 10 CFR Part 50, and
b. Each REPORTABLE EVENT shall be reviewed by the ROC, and the results of this review shall be submitted to the responsible Vice President.
l 6.7 PROCEDURES AND PROGRAMS )
1 l ]kvaverino 7.1 Written procedures shall be established, implemented, and maintained the activities referenced below:
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a. The applicable procedures recommended in Appendix A of Regulatory l Guide 2.33, Revision 2, February 1978.
b. The applicable procedures required to implement the requirements of NUREG-0737.
c. Fuel handling operations.
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d. Surveillance and test activities of safety-related equipment.
e. Security Plan implementation.
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f. Emergency Plan implementation,
g. Fire Protection Procram implementation.
h. PROCESS CONTROL PROGRAM implementation. l
3. OPPSITE DOSE CALCULATION MANUAL implementation.
j. Quality Assurance Program for effluent and environmental monitoring.
O SHOREHAM - UNIT 1 6-9
I I
ADMTNISTRATIVE CONTROLS l
6.7.2 Each procedure of Specification 6.7.1, and changes thereto, shall be ,
reviewed by the ROC prior to implementation. The Plant Manager shall cpprove Station Administrative procedures, Security Plan implementing l procedures and Emergency Plan Implementing Procedures prior to implementation. Other procedures of Specification 6.7.1 shall be approved by the appropriate plant Division Manager or by the Plant Manager prior to implementation. Each Plant Division Manaaer shall be responsible for a j d30ionated set of procedures. These procedures shall be reviewed periodically as set forth in administrative procedures.
6.7.3 Temporary changes to procedures of Specification 6.7.1 may be made provided i
a. The intent of the original procedure is not altered;
b. The change is approved by two members of the unit management staff, at least one of whom is qualified as an operator on shift; and
c. The chance is documented, reviewed by the ROC, and approved by the Plant Manager within 14 days of implementation.
.7.4 The followino programs shall be established, implemented, and maintained:
a. Padioactive Effluent Controls Procram ]
A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining doses to i MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in'the ODCM, (2) shall be implemented by operatino procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The proaram shall include the following elements: ,
1) Limitations on the operability of radioactive liquid and gaseous monitorina instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM.
SHOREHAM - UNIT 1 6-10
-s . :
ADMINISTRATIVE CONTROLS 1
2) Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column ,
2, l 1
3) Monitorina, sampling, and analysis of radioactive liquid and caseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM,
4) Limitations on the annual and quarterly doses or dose l commitment to a MEMBER OF THE PUBLIC from radioactive j materials'in liquid effluents releesed from each unit to l UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part '
50,
5) Determination of cumulative and projected dose contributions from radioactive affluents for the current calendar quarter 1 and current calendar year in accordance with the methodoloay I and parameters in the ODCM at least every 31 days,
' () 6) Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the l
appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a ;
31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I l to 10 CFR Part 50, l
7) Limitations on the dose rate resultina from radioactive '
l material released in gaseous effluents to areas beyond the L SITE BOUNDARY conformina to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1,
8) Limitations on the annual and quarterly air doses resulting i from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,
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SHOREHAM - UNIT 1 6-11 1
t MINISTRATIVE CONTROLS -
9) Limitations on the annual and quarterly doses to a MEMBER OF !'
THE PUBLIC from tritium and all radionuclides in particulate form with half-lives areater than 8 days in caseous !'
effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50,
10) Limitations on the annual dose or dose commitment to any ,
MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190. ;
b. Radiolocical Environmental Monitorino Procram f A program shal1 be provided to monitor the radiation and '
radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the ;
highest potential exposure pathways, and (2) verification of the >
accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The procram shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
1) Monitoring, sampling, analysis, and reportina of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM. ,
2) A Land Use Census to ensure that chances in the use of areas at and Leyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and
3) Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance procram for environmental monitorina.
O SHOREHAM - UNIT 1 6-12
s .
DMINISTRATIVE CONTROLS 6.8 REPORTING REOUIREMENTS I ROUTINE REPORTS l 6.8.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to !
th3 Regional Administrator of the Reaional Office of the NRC'unless ,
ctherwise noted.
ANNUAL REPORTS 6.0.1.1 Annual reports covering the activities of the unit as described below for the previous calendar year shall be submitted prior to March 1 of '
occh year. The initial report uas submitted prior to March 1 of the year th t followed initial criticality.
6.8.1.2 Reports required on an annual basis shall include a tabulation on cn annual basis of the number of station, utility, and other personnel [
(including contractors) receiving exposures greater than 100 mrems/yr and th31r associated manrem exposure according to work and job functions *
.g., operations and surveillance, inspection, routine maintenance, ecial maintenance (describe maintenance), waste processina, and fuel ndlina). The dose assignments to various duty functions may be estimated b2 red on pocket dosimeter, thermoluminescent dosimeters (TLD), or film b:dae measurements. Small exposures totallina less than 20% of the individual total dose need not be accounted for. In the aggregate, at loost 80% of the total wnolebody dose received from external sources should be assioned to specific major work functions. '
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT, 6.8.1.3 The Annual Radiological Environmental Operating Report coverina tha operation of the unit during the previous calendar year shall be cubmitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radioloaical Environmental Monitoring Procram for the reportina period. The material provided shall be consistent with the objectives outlined in (1) the ODCM cnd (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CPR Part 50.
This tabulation supplements the requirements of 20.407 of CFR Part 20.
O SHOREHAM - UNIT 1 6-13
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OADMINISTRATIVE CONTROLS I
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT J 6.8.1.4 The Semiannual Radioactive Effluent Release Report covering the !
Cperation of the unit during the previous 6 months of operation shall be cubmitted within 60 days after January I and July 1 of each year. The ,
rcport shall include a summary of the quantities of radioactive ifquid and COseous effluents and solid waste released from the unit. The material pr;vided shall be (1) consistent with the objectives outlined in the ODCM '
cnd PCP And (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of AppendM 'I to 10 CFR Part 50. l SPECIAL REPORTS 6.8.2 Special reports shall be submitted to the Recional Administrator of tho Realonal Office of the NRC within the time period specified for each rcport.
6.9 RECORD RETENTION 6.9.1 In addition to the applicable record retention requirements of Title 0, code of Federal Reculations, the following records shall be retained r at least the minimum period indicated.
6.9.2 The following records shall be retained for at least 5 years:
a. Records and logs of fuel handling operations.
b. Records and logs of principal maintenance activities,
! inspections, repair, and replacement of principal items of equipment related to nuclear safety.
c. All REPORTALLE EVENTS.
d. Records of surveillance activities, inspections, and calibrations required by these Technical Specifications.
e. Records of chances made to the procedures required by Specification 6.7.1.
f. Records of radioactive shipments,
q. Records of sealed source and fission detector leak tests and results.
O SHOREHAM - UNIT 1 6-14
l MINISTRATIVE CONTROLS
h. Records of annual physical inventory of all sealed source material of record. !
6.9.3 The followina records shall be retained for the duration of tto unit '
Operating License
a. Records and drawina changes reflectina station design modifications made to systems and equipment described in the Final Safety Analysis Report.
b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
c. Records of radiation exposure for all individuals issued monitorina devices in accordance with 10CFR20.202.
d. Records of gaseous and liquid radioactive material released to the environs.
e. Records of training and qualification for current members of the unit staff.
f. Records of quality assurance activities required by the Quality Assurance Manual which are not listed in Section 6.9.2.
a. Records of reviews performed for changes made to procedures or equip. rent or reviews of tests and experiments pursuant to 10 CFR I 50.59.
l h. Records of meetinas of the ROC.
1. R2 cords of analyses required by the radiological environmental monitorina procram that would permit evaluation of the accuracy of the analysis at a later date. This should include procedures effective at specified times and QA records showino that these procedures were followed.
j. Records of reviews performed for chances made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAM.
6.10 RADIATION PROTECTION PROGRAM 6.10 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
O SHOREHAM - UNIT 1 6-15
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MINISTRATIVE CONTROLS :
6.11 HIGH RADIATION AREA 6.11.1 In the lieu of the " control device
or
alarm sional" required by ,
p;ragraph 20.203 (c) (2) of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrems/h but less than 1000 mrems/h shall be barricaded and conspicuously posted as a hiah radiation ,
crea and entrance thereto shall be controlled by requiring issuance of a R2diation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the followings i
a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.
b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made ,
knowledoeable of them.
c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device, who is responsible for providina positive control over the activities within the area and chall perform .
periodic radiation surveillance at the frequency specified by the Health Physics Encineer in the RWP.
6.11.2 In addition to the requirements of Specification 6.11.1 areas accessible to personnel with radiation levels such that a major portion ~of
tha body could receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose areater than 1000 mrems shall be
provided with locked doors to prevent unauthorized entry, and the keys l shall be maintained under the administrative control of the Watch Supervisor on duty and/or the Health Physics Encineer. Doors shall remain
locked except during periods of access by personnel under an approved RWP l which shall specify the dose rate levels in the immediate work area and the moximum allowable stay time for individuals in that area. For indf.vidual arsas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose in excess of 2000 mrsmc** that are located within large areas, such as the containment,
Health physics personnel or personnel escorted by health physics personnel shall be exempt from the RWP issuance requirement durina the performance of their assioned radiation protection duties, provided they l ore otherwise followino plant radiation protection procedures for entry I into high radiation areas.
Measurement made at 18 inches from source of radioactivity.
SHOREHAM - UNIT 1 6-16
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g MMINISTRATIVE CONTROLS I
where no enclosure exists for purposes of locking, and no enclosure can be j r:csonably constructed around the individual areas, then that area shall be !
r ped off, conspicuously posted, and a flashino light shall be activated as a warning device. In lieu of the stay time specification of the RWP, i continuous surveillance, direct or remote (such as use of closed circuit TV l cameras) may be made by personnel qualified in radiation protection pr:cedures to provide exposure control over the activities within the area. i 6.12 PROCESS CONTROL PROGRAM (PCP) !,
Ch2 noes to the PCP: I
a. Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.3j. This documentation shall contain:
1) Sufficient information to support the chance tocether with the appropriate analyses or evaluations justifying the :
chance (s) and
2) A determination that the change will maintain the overall O conformance of the solidified waste product to existino requirements of Federal, State, or other applicable ,
reaulations.
b. Shall become5'e"ffective after review and acceptance by the ROC and t the approval of the Plant Manager.
I 6.13 OFFSITE DOSE CALCULATION MANUAL (ODCM) k l
Chenges to the ODCM:
a. Shall be documented and records of reviews performed shall be l retained as required by Specification 6.9.33 This documentation shall contain:
1) Sufficient information to support the change together with the appropriate analyses or evaluations justifyina the change (s) and O
SHOREHAM - UNIT 1 6-17
i
2) A determination that the chance will maintain the level of l radioactive effluent control required by 10 CFR 20.106, 40 .
CFR Part 390, 10 CPR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of ,
effluent, dose, or setpoint calculations.
b. Shall become effective after review and acceptance by ROC and the approval of the Plant Manager.
c. Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Semiannual Radioactive Effluent Release Report for the period j of the report in which any change to the ODCM was made. Each change shall be identified by markings in the margin of the >
affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e,g., month / year) the chance was implemented. .
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SHOREHAM - UNIT 1 6-18
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APPENDIX B TO FACILITY OPERATING LICENSE NO. ;
t SHOREHAM NUCLEAR POWER STATION, UNIT 1 I
LONG ISLAND LIGHTING COMPANY DOCKET 00. 50-322 l
ENVIRONMENTAL PROTECTION PLAN ,
e (NON-RADIOLOGICAL) o i f
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/%' )T SHOREHAM NUCLEAR POWER STATION l
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- UNIT 1 i
l ENVIRONMENTAL PROTECTION PLAN )
(NON-RADIOLOGICAL) {
TABLE OF CONTENTS l 5;ction Page 1,, 0 OBJECTIVES OF THE ENVIRONMENTAL PROTECTION PLAN................. 1-1 .
2.0 ENVIRONMENTAL PROTECTION ISSUES................................. 2-1 ,
2.1 Aquatic IWsueB.................................................. 2-1 2.2 Terrestrial 188ues.............................................. 2-2 O.0
\ss CONSISTENCY REQUIREMENTS....................................... 3-1 3.1 Facility Design and Operation.................................. 3-1
3.2 Reporting Related to the SPDES Permit.......................... 3-2 ,
t 3.3 Changes Required for Compliance with Other
Environmental Regulations.................................... 3-3 4.0 ENVIRONMENTAL CONDITIONS....................................... 4-1 4.1 Unusual or Important Environmental Events...................... 4-1 4.2 Environmental Monitorina and Other Requirements................................................. 4-1 5.0 ADMINISTRATIVE PROCEDURES f 5.1 Review and Audit.............................................. 5-1 5.2 Records Retention............................................. 5-1
.3 Chances in Environmental Protection P1an...................... 5-2 5.4 Facility Reporting Refluirements............................... 5-2
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\;. 0 OBJECTIVES OF THE ENVIRONMENTAL PROTECTION PLAN l
Th3 Environmental Protection Plan (EPP) is to provide for protection of n;nradioloalcal environmental values during operation of the nuclear fccility. The principal objectives of the EPP are as follows:
[
I (1) -Verify that facility is operated in an environmentally acceptable f manner, as established by the Final Environmental Statement-Operatina l License Stage (FES-bL) and other NRC environmental impact assessments. ;
i (2) Coordinate NRC requirements and maintain consistency with other [
Federal, State and local requirements for environmental protection.
(3) Keep NRC informed of the environmental effects of facility operation and of actions taken to control those effects.
Environmental concerns identified in the FES-OL which relate to water t
quality matters are regulated by way of the New York State Pollutant Diccharge Elimination System (SPDES) permit, issued to licensee, f
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I 2.0 ENVIRONMENTAL PROTECTION ISSUES s
In the FES-OL dated October 1977, the staff considered the environmental [
impacts associated with the operation of the Shoreham Nuclear Power st: tion, Unit 1. Certain environmental issues were identified which j i
required study or license conditions to resolve environmental concerns and ,
to assure adequate protection of the environment.
2.1 Aquatic Issues Specific aquatic issues raised by the staff in the FES-OL were:
(G_,1) The need for discharge related aquatic monitoring programs to confirm that the station's cooling water system with its offshore submerced
, diffuser performs as predicted and its protective of indicencun biota of Long Island Sound, from a thermal and chemical discharge standpoint (FES-OL summary and conclusions and sections 5.4, and 6.3),
(2) The need for intake-related studies to document levels of Antake entrainment and impingement, to determine survival of entrained ichthyoplantkton, and measure the effectiveness of the fish return system in protecting impinged fish (FEE-OL summary and conclusions and sections 5.4, 6.3 and 10.4). -
2-1
pc -
3): The need for monitoring existing wells on the Shoreham site and the Shoreham-West site to detect effects of plant operation on both water ;
level and water quality (FES-OL Section 6.3.3).
Ic;ues (1) and (2) are addressed by the effluent liti?ations, monitorina requirements and other conditions contained in the SPDES permit issued by the New York State Department of Environmental Conservation (NYSDEC). The NRC will rely on the NYSDEC for renulation of matters involving water ,
qus11ty and aquatic biota. NRC requirements with regard to issue (3) are '
specified in section 4.2 of this EPP.
2.2 Terrestrial Issues l
( +
Tha specific terrestrial issues raised by the staff in the FES-OL ares (1) The need to protect Wading River Marsh from deposition of sand and other materials transported from the Shoreham site (FES-OL Summary and conclusions and Sections 4.2, 5.2, 6.2.4 and 6.3.6)
(2) The need for monitorina and mitigating beach erosion (FES-OL Summary and Conclusions and Sections 4.2, 5.2, 6.2.4 and 6.3.6)
() 2-2
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(3)' The need for controlled use of herbicides (FES-OL Section 5.4.1) :
(4) The need for monitoring the mortality of migratory birds resulting from collision with the meteoroloalcal tower and plant structures ;
(FES-OL Section 6.2.4 and 6.3 6) [
WRC recuirements with regard to issues (1) through (3) are specified in >
C^etion 4.2 of this EPP, Issue (4) is covered by section 4.1 of this EPP.
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(x )J 3.0 CONSISTENCY REQUIREMENTS
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I 3.1 racility Desion and Operation j Tha licensee may make changes in facility design or operation or perform tOcts or experiments affecting the environment provided such activities do I
n:t involve an unreviewed environmental question, and do not involve a ch nge in the EPP.* Changes in facility design or operation or performance toots or experiments which do not significantly affect the environment or that are covered by the SPDES permit are not subject to the requirements of this EPP. Activities coverned by Section 3.3 are not subject to the requirements of this section.
( ) fore engaging in additional construction or operational activities which m y'significantly affect the environment, the licensee shall prepare and L racord an environmental evaluation of each such activity. Activities are l
l cxcluded from this requirement if all measurable nonradioloaical effects aro confined to the on-site areas previously disturbed during site proparation and facility construction. When the evaluation indicates that cuch activity involves an unreviewed environmental question, the licensee 1
l chn11 provide a written evaluation of such activity and obtain prior NRC opproval. When such activity involves a change in the EPP, such activity cnd change to the EPP may be implemented only in accordance with an cppropriate license amendment as set forth in Section 5.3 of this EPP OThis provision does not relieve the licensee of the requirements of 10 CFR
.59.
3-1
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~ A proposed change, test or experiment shall be deemed to involve an careviewed environmental question if it concerns (1) a matter which may rosult in a significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in Cny decisions of the Atomic Safety and Licensina Board; or (2) a cignificant change in effluents or design power levels or (3) a matter not. ,
l proviously reviawed and evaluated in the documents specified in (1) of this l J
Subsection, which may have a significant adverse environmental impact.
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Tho licensee shall maintain records of changes in facility design or cperation and of tests and experiments carried out pursuant to this Subsection. These records shall include written evaluations which provide Oe fer ea d
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involve an unreviewed environmental question nor constitute a decrease in I
tho effectiveness of the EPP to meet the objectives specified in Section l 1.0.
I 3.2 _ Reporting Related to the SPDES Permit Ch2nges to, or renewals of the SPDES Permit shall be reported to the NRC within 30 days following the date the approved chance or renewal is roceived. If a permit or certification, in part or in its entirety, is cppealed and stayed, the NRC shall be notified within 30 days following the dcy the stay is aranted..
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a licensee shall notify the NRC of changes to the effective SPDES permit prcposed by the licensee by providing the NRC with a copy of the proposed chtnge at the same time it is submitted to the permitting agency. The licensee shall provide the NRC a copy of the application for renewal of the SPDES permit at the same time the application is submitted to the permitting agency.
3.3 _C_hances Required for Con.pliance with other Environmental Regulations t l Chances in facility design or operation and performance of tests or experiments which are required to achieve compliance with other Federal, StGte and local environmental regulations are not subject to the ,
,quirements of Section 3.1.
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4.0 ENVIRONMENTAL CONDITIONS ,
4.1 Unusual or Important Environmental Events i
I Any occurrence of an unusual or important event that indicates or could ,
result in significant environmental impact causally related to maintaining tho facility shall be recorded and promptly reported to the NRC within 24
'h:urs followed by a written report per subsection 5.4.1. The following are cxcmples excessive bird impaction events, onsite plant or animal disease i cutbreaks, mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973, fish kills, increase in nuisance organisms er conditions, and unanticipated or emeroency discharge of waste water or
mical substances.
No routine monitorino programs are required to implement this condition.
l 4.2 Environmental Monitorina and Other Requirements 4.2.1 Prctection of Wadina River Marsh Tha applicant shall protect Wading River Marsh, including those portions owned by the Applicant, from deposition of sand and other materials tronsported from the facility site. Ultimate control shall be primarily by ground cover, other vegetation and administrative action. Reliance may cico be upon snow fencing and similar physical barriers. There shall be no O
(_ outine reportino requirement associated with this condition.
4-1
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I 4.2.2 Beach Erosion Th3 applicant shall monitor the accumulation and/or erosion of beach sand cnd cravel in the vicinity of the facility site. Any beach material eroded from east of the Applicant's jetties shall be replaced with accumulated l l
CCnd, if any, from Wading River Creek, from the 1000-foot-long intake 1
chtnnel, from between the jetties, and from the east and west sides of the jottles. There shall be,no routine reporting requirement associated with this condition.
'4.2.3 Maintenance of Transmission Line Corridors A
t ,2o use of herbicides within the Shoreham Nuclear Power Station trcnsmission line ccrridors shall conform to the approved use of selected h0rbicides as reaister?d by the Environmental Protection Agency and opproved by State authorities and applied as directed by said authorities.
R3 cords shall be maintained in the appropriate division office concernine h0rbicide use. Such records shall include the following information commercial and chemical names of materials used; concentration of active material in formulations diluted for field uses diluting substances other then water; rates of application; method and frequency of application; Iccation; and date of application. Such records shall be maintained for a p;riod of 3 years in conformance with NYS Department of Environmental Conservation requirements and be made readily available to the NRC upon h~sOquest. There shall be no routine reporting requirement associated with this condition.
4-2
l 0 ADMINISTRATIVE PROCEDURES
.5.1 Review and Audit
-Tho licensee shall provide for review and audit of compliance with EPP. !
L Tho audits shall be conducted independently of the individual or groups rocponsible for performing the specific activity. A description of the ,
crcanizational structural utilized to achieve the independent review and cudit function and results of the audit activities shall be maintained and !
made available for inspection.
5.2 Records Retention ROcords and logs relative to the environmental aspects of maintaining the fccility shall be made and retained in a manner convenient for review and incpection. These records and locs shall be made available to NRC on rcquest.
R cords of modifications to facility structures, systems and components datermined to have the potential to significantly affect the continued protection of the environment shall be retained for the life of the fccility. All other records, data and logs related to this EPP shall be rctained for five years or, where applicable, in accordance with the rcquirements of other agencies.
5-1
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1 5.3 Chances in Shoreham Environmental Protection Plan Request for change in the EPP shall include an assessment of the Cnvironmental impact of the proposed change and supportina justification. .
Implementation of changes in the EPP shall not commence prior to NRC cpprovel of the proposed chances in the form of a license amendment
- incorporating the appropriate revision to the EPP.
5.4 , Plant Reporting Requirements 5.4.1 Nonroutine Reports
( ]) written report shall be submitted to the NRC within 30 days of occurrence ,
of a nonroutine event. The report shall (a) describe, analyze, and ovaluate the event, including extent and maanitude of the impact and fccility operating characteristics, (b) describe the probable cause of the cvant, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event cnd to prevent similar occurrences involving similar components or systems, cnd (e) indicate the agencies notified and their preliminary responses.
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' Evdnts repcrtable under th'is-subsection which also require reports to other
-Fideral',, State-or local agencies shall be reported in accordance with those r; porting requirements in' lieu of the requirements'of this subsection. The
'"- KRC shall'be provided a copy of such report at the same time it'is
'cubmitted to the other agency. .
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ML20005F248

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