Text

Forwards Review of Util 900105 Request to Amend Tech Specs to Reflect Plant Protracted Defueled Condition.Meeting Should Be Scheduled at Site on 900719 & 20 to Discuss Finalizing Plant Defueled Tech Specs
	ML20055D291
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	06/27/1990
From:	Butler W; Office of Nuclear Reactor Regulation
To:	Steiger W; LONG ISLAND LIGHTING CO.
References
	TAC-75846, NUDOCS 9007060119
	Download: ML20055D291 (109)
	v • d • e

i Docket No. 50 322 June 27, 1990 Mr. William E. Steiger, Jr.

Ass.istant Vice President. Nuclear i

Oprations-Long Island Lighting Company Shoreham Nuclear Power Station

P.O. Box 618, North Country Road Wading River,, NY 11792

Dear Mr. Steiger:

TECHNICAL SPECIFICATIONS FOR THE DEFUELED MODE

SUBJECT:

' NUCLEAR POWER STATION, UNIT 1 (TAC NO. 75846), SHOREHAM In your letter dated January 5,1990 was a request that the Shoreham Nuclear 3

Power Station Unit 1, Technical Specifications be amended to reflect the plant's i

protracted-defueledcondition.

Enclosed is the staff's initial review of that request.

t Please review the NRC staff's comments. Also, we request that a meeting be scheduled at the site on July 19 and 20, 1990, to discuss finalizing Shoreham's Defueled Technical Specifications.

Sincerely,

/S/

Walter R. Butler, Director Project Directorate 1 2 i

Division of Reactor Projects.1/II Office of Nuclear Reactor Regulation y,

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Enclosure:

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wAssiwoTow. o. c. :osos June 27, 1990 Docket No. 50-322 g

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Mr. William E. Steiger, Jr.

Assistant Vice President-Nuclear Operations Long Island Lighting Company Shoreham Nuclear Power Station P.O. Box 618, North Country Road Wading River, NY 11792-

Dear Mr. Steiger:

SUBJECT:

TECHNICAL SPECIFICATIONS FOR THE DEFUELED N0DE, SHOREHAM NUCLEAR POWER STATION, UNIT 1 (TAC NO. 75846)

In your letter dated January 5 1990 was a request that the Shoreham Nuclear Power Station, Unit 1. Technical Specifications be amended to reflect the plant's protracted defueled condition.

Enclosed is the staff's initial review of that request.

Please rW iew the NRC staff's comments. Also, we request that a meeting be scheduled at the site on July 19 and 20, 1990, to discuss finalizing Shoreham's Defueled Technical Specifications.

Sincerely, f

G Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

Defueled Technical Specifications With Comments cc w/ enclosure:

See next page

c-Mr. William E. Steiger, Jr.

Shorehala Nuclear Power Station long Island Lighting Company cc:

Victor A. Staffieri. Esq.

MHB Technical Associates General Counsel 1723 Hamilton Avenue Long Island Lighting Company Suite K 175 East Old County Road San Jose, California 95125 i

Hicksville, New York 11801 Richard M. Kessel W. Taylor Reveley, III, Esq.

Chairman & Executive Director Hunton & Williams New York State Consumer Protection Post Office Box 1535 Board 707 East Pain Street Room 1725 Richmond, Virginia 23212 250 Broadway New York, New York 10007 Mr. Lawrence Britt Shoreham Nuclear Power Station Jonathan D. Feinberg, Esq.

Post Office Box 618 New York State Department Wading River, New York 11792 of Public Service Three Empire State Plaza Mr. L. Calone Albany, New York 12223 Plant Manager Shoreham Nuclear Power Station Fabian G. Palomino, Esq.

Post Office Box 628 Special Counsel to the Covernor Wading River, New York 11792 Executive Chamber - State Capitol Albany, NY 12224 Resident Inspector Shoreham NPS Martin Bradley Ashare, Esq.

U.S. Nuclear Regulatory Commission Suffolk County Attorney Post Office Box B H. Lee Dennison Building Rocky Point, New York 11778 Veteran's Memorial Highway Hauppauge, NY 11788 Regional Administrator, Region I U.S. Nuclear Regulatory Commission Robert Abrams, Esq.

475 Allendale Road Attorney General of the State King of Prussia, Pennsylvania 19406 of New York ATTN: Charles Donaldson, Esq.

Ms. Donna Ross New York State Department of Law New York State Energy Office Consumer Protection Bureau Agency Building 2 120 Broadway Empire State Plaza 3rd Floor Albany, New York 12223 New York, NY 10271 m

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Long Island Lighting Company

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cc:

James P. McGranery, Jr., Esq.

Leonard Bickwi'., Jr., Esq.

Dow, Lohnes and Alberson Miller & Chevalier, Chartered Suite 500 Metropolitan Square 1255 23rd Street, N.W.

655 Fifteenth Street, N.W.

Washington, D.C.

20037 Suite 900 t

Washington, D.C.

20005-5701 Dr. A. David Rossin Resources Conservation L. Hill-Organization New York Power Authority Suite 320 123 Main Street 101 First Street White Plains, New York 10601 Los Altos, CA 94022 David J. McGoff Commissioner James T. McFarland-Associate Deputy Assistant New York Public Service Commission Secretary for Reactor Deploynent 814 Ellicott Building.

11.5. Department of Energy 295 Main Street Washington, D.C.

20545 Buffalo, New York 14203 b

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5 STCTION 1.0 DEFIN2TIONS I

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i 1.0 DEFINITIONS The following terms are defined so that uniform interpretation of these specifications may be achieved.

The defined terms appear in capitalised i

type and shall be applicable throughout these Technical Specifications.

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1.1 ACTION Ohall be that part of a 5pecification whic pres somettT2 3

under designated conditi~ons pMd y lld->

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C-l CMANNEL CALIBRATION 1.2 A CHANNEL CALIBRATION shall be the adjustment, as necesshry, of the channel output such that it responds with the necessary range and accuracy to know'n values of the parameter which the channel monitors.

The CHANNEL CALIBRATION shall encompass the entire chann11 includine the sensor and alarm and/or trip functions, and shall ine.lude the

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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.

CHANNEL gNjg, 2.3 A CHANNEL CRECK shall be the qualitative assessment of channel behavior during operation by observation.

This determination shall i

include, where possible, comparison of the channel indication and/or status with other indications and/or status derived from independent instrument channels measuring the same parameter.

CHANNEL TUNCTIONAL Jg 2 1.4 A CHANNEL TUNCTIONAL TEST shall be s.

Analog channels - the injection of a simulated signal into the channel as close to the sensor as practicable to verify OPERABILITY including alars and/or. trip functions and channel failure trips, b.

31 stable channels - the injection of simulated signal into.the sensor to verify CPERASILITY including 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

&A&1happelistested.

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DEFINITIONS g a n gyg poTAfl0NS l

1.y The FREQUENCY MOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.1.

MEMBER (8) 0F THE.PUBL1.C l'.y MEMBER (8) 0F THE PUEl.JC shall include all persons who are not 3

occupationally associated with the plant.

This category does not j

include employeeg. of the utility, its contractors or vendors.

Also excludad from this category are persons who enter the site to ser'vice equipment or to make deliveries.

This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

CFFSITE DOSE CQ CULATION MANUAL (CDCM) 1.$ The CFFSITE DOSE CALCULATION MANUAL' (CDCM) shall contain the s

methodolocy and parameters used in the calculation of offsite doses-resultino from radioactive gaseous and liquid effluents, in the calculation of caseous and liquid affluent monitoring Alarm / Trip 8etpoints, and in the conduct of the Environmental Radiological l

Monitorina Procram.

The CDCM shall also contain (1) the Radioactive Effluent controls and Radiological Environmental Monitoring Programs required by Section 6.7.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Semiannual-radioactive Effluent Release Reports required by Specifications 6.8.1.3 and 6.8.1.4.

OPERABLE - OPERABILITY 1.4 A system, subsystem, train, component or device shall be OPERABLE or I

hve OPERABILITY when it is capable of performine its specified function (s) and when all necessary attendant instrumentation, controls, electrical power, cooling or seal water, lubrication or i

other auxiliary equipment that are required for the system, subsystem,

.4 train, component or device to perform its function (s) are also capable of performing their related support function (s).

SHOREHAM - UNIT 1 1-2

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-2.13 An UNRESTRICTED AREA shall be any area-at or beyond the SITE 1011NDARY access.to which is not controlled by:the licensee for purposes of 4

protection of individuals from exposure to radiation and radioactive materials, or any area:within the SITE SOUNDARY used for residential quarters or for industrial, commercial, institutional and/or.-

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DEFINITIONS
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TABLE _.1.1 SURVEILLANCE FREQUENCY WOTATION NOTATION FREDUENCY s'
At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
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At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
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At least once once per 7 days.
M At least once per 31 days.
l Q
At least once per 92 days.
ll SA-At least once per 184 days.
- A At least once per 366 days.
- R-At least once per-18 months (550 days)
N.A.
Not applicable..
P Completed prior to each release.
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1 Sections 3.0 and 4.0 LIMITING CONDITIONS FOR FUEL BANDLING OPERATION 1lt AND-l SURVEILLANCE REQUIREMENTS-l i
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T 3.0.1 Compliance with the Limiting conditions w.
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specifications is required during the y
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pecified therein except that upon failure to seet the Limiting conditions ft: *r:1 n.r.01;ng up....; =, the associated v>
ACTION requirements shall be met.
l 3.0.2 Noncompliance with a specification shall exist when the re'quirements of the Limiting Condition 0;. P;;l 5:r'lin ; Opx;^.in and associated ACTION requirements are not met within the specified time intervals.
If the Limiting condition f;hp.: tie-is restored prior to expiration of the
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specified tima interv
, e,ompletion of the Action requirements is not required.
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3.0.3 Commencementgof fuel handling operations shall not be made when the conditions for the Limiting conditions f:: Nel M-'li- ; 0; r.^.ler.- are not l'
met and the associated ACTION requires suspension of fuel handling operations if they are not met within a specified time interval.
Fuel when conformance to themly,q made in accordance with the ACTION requiremen handlino operations may b ermits continued pgiratiop of fuel handling for an unlimited period of time W go,.at 'a./- A,4,x,4.,4 Mr$.
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h4 SURVEILLANCE REOUIREMENTS
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Surveillance Requirements shall be met durin%pa.tJNnLs-rt c%
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4.0.1 i
conditions specified for individual Limiting Conditions,0;; T;;l ::n dling 0;er ti:n.
4.0.2 e
urveillan Reiihaireme 1
be perf within t fie urveil e interva h a maxim owable on not to c
exceed 4o
.e specifi rveillance rval.
4.0.3 Tailure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition r
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The-time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed.
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.eutae " r if 't ci the-ActIorTequirementr-ere~ terr ther24-hourew-Surveillance requirements do not have to be performed on inoperable 4.&d Q
pf wn 4.0.4 Commencementjof fuel handling operations shall not be made unless44 tNe Surveillance Requirement (s) associated with Limiting conditions semi 7;.1 ::er.01174 0;:retfr-have been performed within he applicable surveillance interval, ; ;; eth: ui;. ep.:iffe'.
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Entry into n i...-....,.... specified ition s all t
less veill ne equirpent(s) associate,d ith a,kT iting'
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pes.TW,morovision'e sta notpe ont p io r as prwfse c
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g4.0.5 Surveillance Requirements for inservice inspection and testing of ASME 1
Code Class-1, 2, and 3 components shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and pressure Vessel Code and applicable Addenda as required by 10 CFR50,Section50.55afg),exceptwherespecificwrittenreliefhas I
been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).
4' b.-
-Surveillance intervals specified in Section XI of the ASME Sc11er and Pressure Vessel Code and applicable Addenda for the inservice
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inspection and testing activities required by the ASME Boiler and
.i Pressure Vessel Code an'd applicable Addenda shall be applicable as h
follows in these Technical Specifications:
L ASHE Sc11er and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testing l
inspection and testine activities activities l
Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days semiannually or every 6 months At least once per 184 days t
Every 9 months At least once per 276 days 1
Yearly or annually At least once per 366 days I
c.
The provisions of Specification 4.0.2 are applicable to the above required frequencies for performing inservice inspection and testing 1.ctivities, d.
Perfo~rmance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
e.
Nothing in the ASME Boiler and Pressure Yessel Code shall be construed to supersede the requirements of any Technical Specification.
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INSTRUMENTATION 1
M MONITORING INSTRUMENTATION LIMITING CONDITION FOR FUEL' HANDLING OPERATION 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 specified limits APPLICABILITY:
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ACTIQH i
a.
With an Area Monitor instrumentation channel alarm / trip setpoint exceeding th's value 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.
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~ SURVEILLANCE REQUIREMENTS 4.1.1.2 Each of the above-required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL '
CHECK, CHANNEL TUNCTIONAL TEST and CHANNEL CALIBRATION operations for the-conditions and at the frequencies shown in Table 4.1.1.2-1.
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CHANNELS APPLICABLE AIARM MEASUREMENT JMSTPUV.pTATION gggggg CONDITION ggZggg2 gggg gj
1. Area Monitors l-
a. Criticality Monitors
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Storage Vault. 2**
f 20 mR/hr 10 I to 10 mR/hr 1
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2) Spent Fuel 2**
Storage Pool is 9
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3 -3.1.1.2-1 (Continued) 2Apl A119.N_M0_NITpriqJ_R3f]tpMEEtA21QR 29J} FOTATIONE
'*Whenever fuel is in.the Storage Vault or Spent Fuel Pool.
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These two areas are monitored by the same two detectors.
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MDIAT30)I MpfUj2ggg INSTRUMENTATION E ZISE IIbl.Et E I
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- ACT20N 1 continuous monitor with the same ala setpoint-is CPERABLE in the vicinity of the. ins'alled itor,t fLi =ar 2-b t
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C e ""-i ;,._._ns ivria; =f.cperform area surveys 'of the monitored area wijrh portable.aonitoring instrumentation at least once r 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . /
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RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUJREMENT)
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CRANNEL FUNCTIONAL CHANNEL CE i
INSTRU Q TATION N
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. 1._* Acus Monitors a.
Criticality Monitors 1)
New Fuel Storage SS M
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2) ' Spent Fuel 8 8 M
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1 INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION
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LIMITING CONDITION FOR FUEL RANDLING OPERAT!0N 3.1.2.3 The seismic monitoring instrumentation sh>wn in Table 3.1.1.3-1 j
ahall be OPERABLE.
APPLICABILITY:' 2 h [/
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a.
With one or more of the above required seismic monitoring 3
instruments inoperable for more than 30 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 instrument (s) to y
CPERABLE status.
l SURVEILLANCE REOUIREMENTS 4.1.2.3;I Each of the above required seismic monitoring instruments shall be demonstrated CPERABLE by the performance of the CHANNEL CHECK, CHANNEL L
FUNCTIONAL TEST, and. CHANNEL CALIBRATION operations at the frequencies l
shown in Table 4.1.1.3.1-1.
4.1.1.3.2 Each of the above required seismic monitorina instruments actuated durina a seismic event areater than or equal to 0.01 e shall be restored 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 retrieved from actuated instruments and analyzed to determine the maanitude-
=of the vibratory ground motion.
A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.8.2 within lo days describing the meanitude, frequency spectrum, and resultant effect upon' station features important to safety.
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IbEkl 3.1 1 3-1 sElsMIC MONITORING INSTRUMENTAT[gg MININUN.
MEASUREMENT INSTRUMENTS INSTRUMENTS gg SENSOR p>CATIQN M,
OPERABLE 1.
Triaxial Time-History Accelerographs a.
Primary Containment Mat, outside 0.01-1 g
'l and adjacent to primary containment wall b.
Outside Primary Containment Wall 0.01-1 g 1
El 131'-7" c.
Free Field 0.01-1 g 1
2.
Triaxial seismic switches a.
Primary containment Mat 0.01 g 1*
3.
Triaxial Response-Spectrum Recorders a.
' Containment Mat El 8'-0" 0.01-2 g 1*
b.
Reactor Pedestal Wall - E1.70'-8" 0.01-2 g 1.
With reactor control room indication.
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SEISMIC' MONITORING-INSTRUMENTATION gRVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL
, - !NSTRUMENT g SENSOR LOCATIONS
SEEEE, 2E12 CALIsnATION 1.
Triaxial Time-History Accelerographs a.
Primary Containment Mat, outside and adjacent to primary containment wall M*
SA R~
Wall - El 131'y Containment Outside Primar b.
-7" M*
SA R
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' Free Field M*
SA R
2.
Triaxial Seismic Switches a.
Primary Containma.nt-Mat **
M SA R-l 3.
Triaxial Response-spect rum Recorders a.
' Containment Mat E3.8'-0"**
M SA R
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Reactor Pedestal vall El 70'-8" n
Except-seismic triacer
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INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR FUEL HANDLING OPERATION i
l 3.1.1.4 The meteorological monitoring instrumentation channels on the 400-ft tower shown in Table 3.1.1.4-1 shall be OPERABL2.
APPLICABILITY: 4t 211 tir:;.
ACTION:
a.
With one or more meteorological monitoring instrumentation 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 CPERABLE status.
SURVEILLANCE RECUIREMENTS 4.1.1.4 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.1.1.4-1.
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METEOROLOGICAL MONITORING JNSTRIMENTATION
.1 MINIMUM' INSTRUMENTS INstnUMENT 2ZEMH Wind speed-Elev.- 33/150 ft 1
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Wind' Direction Elev. 33/150 ft
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,'3a Air Temperature Difference Elev. 33/150 ft.
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o-IABLE 4.1.1.4-1 METEOROLOGICAL MONITORING INSTRUMENTATION $_URVIILIANCE REQUIREMENTI CHANNEL:
CHANNEL-INSTRUMENT Al[1GE CALIBRATION i
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Wind Speed
'Elev. 33/150:ft, D
SA 2.
. Wind Direction Elev.33/150 ft D
SA 3.
Air Temperature Difference Elev. 33/150 fu D'
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' 3/4.2.1 SECONDARY CONTAINMENT
' SECONDARY CONTAINMENT INTEGRITY L
' LIMITING CONDITION FOR FUEL HANDLING CPERATION 3.2.1.1 -
0D TAINMENT INTEGRITY shall be maintained.
APPLICABILI Y:A en irradiated fuel is being. handled in the secondary ncontainment.
ACTION:
Without SECONDARY CONTAINMENT ' INTEGRITY, suspend handling of Arradiated fuel-in the secondary containment.
SURVEILLANCE REQUIREMENTS 4.2.1.1 SECONDARY CONTAINMENT INTEGRITY shall be demonstrated bys 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 vacuhm water gauge.
b.
Verifying at least once per 31 days thats is 1.
All secondary containment equipment hatches are closed and sealed.
2.-
.At least one door in each access to the secondary l-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.
.s SHOREHAM - UNIT 1 3/4 2-1 D
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J/,f.3 PLANT sin. TIM _.E 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-microcurfes of beta and/or gamma 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:
J55::ambbe&mee,- h g
ACTION:
With a sealed source havina removable contamination in excess of the above limit, withdraw the. sealed source from use and either:
i 2.
Decontaminate sad repair the sealed source, or i
2.
Dispose of the sealed source in accordance with Commission Regulations.
SURVEILLANCE REQUIREMENTS 4'.3.1.1 Test Reeuirements - Each sealed source shall be tested for leakage 1 and/or contamination by:
a.
The' licensee, or b.
Other persons specifically authorized by the commission or an E
Acreement state.
The' test aethed shall have a detection sensitivity of at least 0.005
-microcurie per test sample.
.4.3.1.2 Test Frecuenc;es - Each category of sealed sources, excluding startup sources and.f;,ssion detectors.previously subjected to core flux, shall,be tested at the frequency described below, a..
Scurces 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 Hydrogen 3, L
and 1.
2.
In any form other than gas.
L i
' SHOREHAM - UNIT 1 3/4 3-1 1
1 PLANT SYSTEMS 1-SURVEILLANCE REOUIREMENTS' (ContinU*d)
^
b.-
Stored soutees not in use - Each sealed source and fission detector s;)all be testes 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.
It,artuo sources and' fission detectors - Zach 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 leakana tests reveal the presence of creater than or equal to 0.005 microcurie of removable' contamination.
(-
SHOREHAM - UNIT 1 3/4 3-2 i:
1
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4 e
fLANT SYSTEMS 3/4.3.2 SETTLEMENT OF REACTOR BUILDING TOTAL SETTLEMENT LIMITING CONDITION FOR FUEL HANDLING OPERATION 3.3.2.1 The total settlement of the Reactor Building shall not exceed 4.0 inches (80% of the limiting value specified in Table 3.3.2.1-1).
APPLICABILITY ?t ;11 ti r. d Ade i
ACTION:
With the total settlement of the Reactor Building reaching 4.0 inches (80%
of the ILmiting' settlement value specified in Table 3.3.2.1-1), conduct an engineering review of field conditions and evaluate the consequences 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.
SURVEILLANCES REOUIREMENTS 4.3.2.1 The total settlement of the Reactor Building shall be determined to the nearest 0.01 foot by measurement and calculations 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 reading.
b.
At least once every 24 months thereafter.
0.10 inch from previous reading.
SHOREHAM - UNIT 1 3/4 3-3 i
PLANT SYSTEMS
\\
DIFFERENTIAL SETTLEMENT ACROSS THE STRUCTURE LIMITING CONDITION FOR FUEL BANDLING CPERATION 3.3.2.2 The differential settlement across the Reactor Building shall not exceed 1.6 inches (80% of the limiting va'lue specified in Table 3.3.2.1-1).
APPLICABILITY: it ;11 ti ::.,8
/hd p
hSII.5LN With the differential settlement across the Reactor Building exceeding 1.6 inches (80% of the allowable settlement value spoeified in Table 3.3.2.1-1), conduct an enaineering review of field conditions and evaluate the consequences 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 existino and possible continued settlement, and the remedial action to be taken, if any, includine the date of the next survey.
SURVEILLANCE REQUIREMENTS 4.3.2.2 The differential settlement across the Reactor Building shall be determined to the nearest 0.01 foot by measurement and calculation a.
At least every 6 months 1.
Until observed settlement has stabilized *, and 2.
Whenever previously stabilized
settlement exceeds 0.10 inch since the previous reading.
b.
At least once every 24 months thereafter.
0.10 inch from previous reading.
SHOREHAM - UNIT 1 3/4 3-4
e.
11bMT BYSTRKE PENETRATION DIFTERENTIAL SETTLEMENT - STRUCTURE TO SOIL LIMITING CONDITION FOR FUEL HANDLING OPERATION 3.3.2.3 The penetration differential settlement - structure to soil shall not exceed 0.70 inch (80% of the limiting value specified in Table 3.3.2.1-1).
APPLICABILITY: At h
/
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 conditiens and evaluate l
the consequences 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.
SURVIILLANCE REQUIREMENTS 4.3.2.3 The penetration-differential settlement - structure to soil shall be determined to the nearest 0.01 foot by hieasurement 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 reading.
SHOREHAM - UNIT 1 3/4 3-5
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Igg &[ 3.3.2.1-1
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LIMITING VALUES-OF SETTLEMENTS OF-REACTOR BUILDING (RB) j H
LIMITING VALUE SETTLEMENT (inches) 11.
Total absolute settlement 5.0 i
2.'
Differential settlement across RS (Tilt).
2.0
3.
Penetration differential settlement (between structure to soil for differential settlement of buried pipes)
O.9
'I 1
=I SHOREHAM - UNIT 1 3/4 3-6 I
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i 3/4.4.
ELECTRICAL POWER SYSTEMS 3/4.4.1' A.C. SOURCES LIMITING CONDITION FOR FUEL HANDLING OPERATION
\\1 3.4.1 One circuit between the offsite smis etwork and the pnsite ti be CPERABLE W
, We gf.L distributiogs APPLICAB7tITY p en handling irradiated fuel in the secondary containment.
O' l
With the o N A.C. electrical power sourcedinoperable suspend i
s handling of irradiated fuel in the secondary containment and crane operations over the spent fuel storage pool when fuel assemblies are stored therein.
i SURVEILLANCE REQUIREMENTS l
The above required (_..Q_,;Abd./g/:n+~' w /c)u.. :'*-4 +=
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4.4.1 e=a an4 - f :.
.....::t ere th: entit: C1;;; 15 d4=+vihutien f:t=,shall'be determined OPERABLE at least once per 7 days by verifying correct breaker alignments and indicated power availability.
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SHOREHAM - UNIT 1 3/4 4-1 4
-ELECTRICAL POWER SYSTEMS 1
c IU 3/4.4.2 ONSITE POWER DISTRIBUTION SYSTEMS LIMITING CONDITION FOR FUEL RANDLING OPERATION 3.4.2' As a minimum, two of the following A.C. power distribution system divisions'shall be energized:
s.
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, 131Y and 1118, c) 120-volt A.C. distribution panels R1, R2, and R3.
l 2.
Division 2 consisting of a),
41'60-volt A.C. bus 102 b) 480-volt A.C. bus 112 and NCCs 1120 through 1129, 112W and 112X.
c)'
120-volt A.C. distribution panels in 31, 32 and 33.
3.
Division 3 consistino 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.
OhAdhirds APPLICABIL7TY:
hen handling irradiated fuel in the secondary containment ACTION:
/. With en) Jam > divisions of'the above required. A.C. divisions-not eneralsed, EL' s and handlina et tyradiated fuel in the.sec,ondary cent inment.t +a wk, 4
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' SURVEILLANCE REOUIREMENTS O
'4.4a2' At least the above required power distribution system divisions shall be determined energized at least once per 7 days by verifying correct breaker alignment and voltage on the busses and power availability to the MCCs and the-panels.
SHOREHAM - UNIT 1 3/4 4-2 l
l'
a-4 ELECTRICAL' POWER SYSTEMS q-LC. SOURCFS *MMIEIBEBA LIMITING CONDITION FOR OPERAT N
'3.8.2.2 As a' minimum, two of the following three divisions of the D.C.
electrical power sources system shall be OPERABLE with:
a.
Division 1, consisting of:
1, 125 volt battery A1.
2, 125 volt charger, b.
Division 2, consisting of:
1.
125 volt battery Bl.
2.
125 volt charger, c-Division 3, consisting of:
l '.
125 volt battery C1, 2.
125. volt charger C1.
APPLICABILITY:
GFEhnilunnu cunut: 1vna,, i d ACTION:
a.
With two or more of the Division 1, Division 2 and Division 3
' batteries and/or chargers of the above required D.C. electrical-5,
(~
power sources inoperable, suspend CORE ALTERATIONS, handling of
~'~
irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.
b.
The provisions of 5pecification 3.0.3 are rot applicable.
SURVEILLANCE REQUIREMENTS 4.8.2.2 At=least the above required 125 volt batteries and charger shall be demonstrated OPER4BLE per Smeillance Requirement 4.8.2.1.
"When handling irradiated-fuel in the secondary containment.
I I
SHOREHAM - UNIT 1 3/4 8-13 l
2 8
L' 3/4.5 PUEL MANDLfWG OPERATIONS 3/4.5.1 COMMUNICATIONS LIMITING CONDITION FOR FUEL MANDLING CPERATION 3.5.1 Direct communication shall be maintained between the control room andrefuelinep}afrn ersonnel.
APPLICAR111TY:
Whenever handling irradiated fuel.
AEU9.He When direct communication between the control room and refueline platform personnel cannot be maintained, immediately suspend handling of irradiated fuel.
EURvtILLANCE Rt002REMENTS 4.5.1 Direct communication between the control room and refueline platform personnal 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 Aandling of irradiated fuel.
(
1 4 9 e
9 SHOREF.AM - UNIT 1 3/4 5-1
)
FUEL MANDLING CPERATIONS
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3/4.5.2 REFUELING PLATFORM LIMITING CONDITION FOR FUti MANDLING CPERATION l
3.5.2 The refueline platform d used for handling fuel assembliesorcontrol)rde.2,-ghalgbeCP '
-A,e
.4 D)(%WJb MARILITY / guring ha oling of fuel assemblies or control rods.
A O'
4h With the requirements for refu ing platform CPERABILITY not satisfied, suspend use of tr; ineper251 refueling platform ti"da==at from operations involving the handling of control rods and fuel assemblies after placing the load in a safe condition.
SURVEILLANCE REQUIREMENTS j
4.5.2 Each refuelino platform crane or hoist used for handline of control rods or fuel assemblies shall be demonstrated CPL.*ABLE within 7 days prior to the start of such operations with that crane or hoist by:
Demonstratino operation of the overload cutoff on the main hoist a.
(.
when the load exceeds 1200 + 50 pounds.
i b.
Demonstrating operation of the overload cutoff on the frame mounted and monorail hoists when the load exceeds 1000 1 50 4
pounds.
Demonstrating the operation of the uptravel mechanical cutoff on c.
the frame mounted monorail hoists when uptravel brings the top of active fuel assembly to 7 feet below the normal fue1 storace pool water level.
d.
Demonstrating operation of the slack cable cutoff on the r..ain hoist when the load is less t:han 50125 pounds.
SHORERAM - UNIT 1 3/4 5-2 4
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j Demonstratine operation of the loaded interlock on thy main hoist j
e.
when the load exceeds 485 1 50 pounds.
f.
Demonstrating operation of the loaded interlock on thg auxiliary l
hoist when the load exceeds 400 g, 50 pounds.
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sHORIMAM - UNIT 1 3/4 5-3 P
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3/4.5.3 CRANE TMVEL LIMITING CONDITION FOR FUEL RANDLING CPERATION 3.5.3 Loads in excess of 1200 pounds shall be prohibited from travel over the spent fuel storage pool racks with fuel assemblies in the spent fuel storsee pool racks and the spent fuel shipping cask movement shall be prohibited from travel over the refueling floor,except when moved,by the CPERABLE polar crane.
I APPLICASILITY:
At all tirrt.
A
~/
ASIl9E8 A
'l With the requirements of the above specification not satisfied, place the crane load in a safe condition.
l l
SURVEILLANCE REQUIREMENTS i
4.5.3 The polar erane shall be demonstrated CPERABLE:
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 storace pool racks or nevement of the spent fuel shippine cask over the refuelino floor by:
1.
Verifyino the redundancy.cf the crane brakes, sear trains, reevino system, and load attaching points by visual inspection.
2.
Demonstratino CPERASILITY 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 330.2, 1976..
b.
By performance of a wire rope inspection in accordance with ANSI 330.2, 1976.
The wire rope shall be replaced should any of the replacement criteria of ANSI 330.2 be met.
SHORIHAM - UNIT 1 3/4 5-4 y.,,%,,-..,-,,+,.-,n.me..
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FUEL MANDLING OPERATIONS I
3/4.5.4 WATER LEVEL - SPENT FUEL STORAGE POOL f
LIMITING CONDITION FOR FUEL MANDLING CPERATION l
4 3.5.4 At least 21 feet of water shall be maintained over the top of trradiated fuel assemblies seated in the spent fuel storace pool racks.
..tcli^.ir:.;d;
'A APPLICA97L77Y:
gag, With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations with loads in the spent fuel storace pool area after placin he fyel assemblies and crane load in
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.p. ~.r SURVE!LLANCE RICU2REMENTS 4.5.4 The water level in the spent fuel storace pool shall be determined to be at least at its minimum required depth at least once per 7 days.
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SHOREHAM - UNIT 1 3/4 5-5 1
j INSTRUMENTATION FIRE DETECTION INSTRUMENTATION
(
LIMITING CONDITION FOR OPERATION N
i d
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l 3.3.7.9 As a minimum, the fire detection instrumentation for each fire k
detection zone shown in Table 3.3.7.9 1 shall be OPERABLE.
APPLICABILITY:
Whenever equipment protected by the fire detection instrument h
is required to be OPERABLE.
h ACTION:
M\\
a.
With the number of OPERABLE fire detection instruments in one or 5M more zones:
1.
Less than, out more than one half of, the Total Number of Instruments shown in Table 3.3.7.9-1 for Function A, restore the inoperable Function A instrument (s) to OPERABLE status v
within 14 days or within 1 bour establish a fire watch patrol to inspect the zone (s) with the inoperable instruments (s) at least once per hour, unless the instrument (s) is located in an (Note 1) inaccessible zone, then inspect that inaccessible zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the air temperature at least once per hour at the locations listed in Specification
(
4.6.1.7 or Specification 4.7.9.
2.
One less than the Total Number of Instruments shown in Table 3.3.7.9-1 for Function B, or one-half or less of the Total Number of Instruments shown in Table 3.3.7.9 1 for Function A, or with any two or more adjacent instruments inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instruments (s) at least once per hour, unless the instrument (s) is located in an (Note 1) inaccessible zone, then inspect that inacces-sible zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the air tem-perature at least once per hour at the locations listed in Specification 4.6.1.7. or Specification 4.7.9.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
~
SURVEILLANCE REQUIREMENTS 4.3.7.9.1 Each of the above required restorable type fire detection instruments which are accessible during unit operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST.
Fire detectors which are not accessible due to specific unit operating conditions i
Note 1:
A zone may be declared to be inaccessible during specific operating conditions (e.g. containment during unit operation, HPCI/RCIC during system testing, main steam tunnel during unit operation).
SHOREHAM - UNIT 1 3/4 3-81
~
}
~
INSTRUMENTATION 4
FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTOOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or when the specific detector becomes accessible, unless performed in the previous 6 months.
4.3.7.9.2 The supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.
4.3.7.9.3 For nonrestorable spot-type detectors, after the fifteenth year at least two detectors out of every hundred, or fr6ction thereof, shall be removed every five years and sent to a testing laboratory for tests.
The detectors that have been removed shall be replaced with new detectors.
If a failur3 occurs on any of the detectors removed, additional detectors shall be removed and tested as a futher check on the installation until there is proven to exist either a general problem involving faulty detectors or a localized problem in-volving only one or two defective detectors.
l 1
l SHOREHAM - UNIT 1 3/4 3-81a
TABLE 3.3.7.9-1 FIRE DETECTION INSTRUMENTATION SAFETY-RELATED ZONE TOTAL NUMBER OF INSTRUMENTS
HEAT SM0KE FLAME Ili7y)
Ili7yI Ii7y7 1.
Control Building Emergency Switchgear Room 101 0/6 6/0 Emergency Switchgear Room 102 0/6 6/0 Emergency Switchgear Room 103 0/6 6/0 Battery Room A 0/2 3/0 Battery Room B 0/2 4/0 Battery Room C 0/3 5/0 Diesel Generator Room 101 0/9 1/0##
3/0 Diesel Generator Room 102 0/11 -
1/0##
3/0 1/0##
3/0 Diesel Generator Room 103 0/10 Relay Room 0/24 14/0 HVAC Equipment Room El 44'-0" 3/0 HVAC Equipr.ent Room El. 63'-0" 5/0 Chiller Equipment Room El. 44'-0" 10/0 Chiller Equipment Room El. 63'-0" 10/0 i-CRAC - FLT 2A E1. 63'-0" 4/0 g.
l CRAC - FL.T 2B E1. 63'-0" 4/0 CRAC CR Exh E1. 63'-0" 1/0 i
Corridor 8 E1. 25'-0" 5/0 Corridor 9 E1. 25'-0" 3/0 2.
Reactor Building Primary Containment #
4/0 Secondary Containment El. 8'-0" 30/0 Secondary Containment E1. 40'-0" 38/0 Secondary Containment El. 63'-0" 14/0 Secondary' Containment E1. 78'-7" El. 95 -3", & 101'-6" 4/0 42/0 Main Steam Tunnel E1. 76'-5" 11/0**
Secondary Containment El. 112'-9".
2/0 55/0 Secondary Containment E1. 126'-9" 7/0 Secondary Containment'h" E1. 150'-9" & 159'-
5/0 27/0 Secondary Containment E1. 175'-9" 3/0##
MG Room 111 El. 150'-9" 4/0 MG Room 112 E1. 150'-9" 3/0 MG Room 113A El. 161'-0" 4/0 g,
l SHOREHAM - UNIT 1 3/4 3-82 l
1 1
TABLE 3.3.7.9-1 (Continued)
FIRE DETECTION INSTRUMENTATION j
SAFETY-RELATED ZONE TOTAL NUMBER OF INSTRUMENTS
HEAT SMOKE FLAME l
M)
M M
MG Room 113B E1. 161'-0" 3/0 MCC West Room E1. 112'-9" 2/0 MCC East Room El. 112'-9" 3/0 Remote Shutdown Panel Enclosure E1. 63'-0" 0/2 L
HPCI Turbine E1. 8'-0" 0/6 RCIC Turbine E1. 8'-0" 0/5 1TK607R Horizontal Cable Trays 2/0 1TX600R Vertical Cable Tray"s 5/0 RBSYS - FLT - 1A E1. 112'-9 2/0 l
RBSYS - FLT - IB E1. 112'-9" 2/0 L
MCC Room E1. 40'-0" 2/0 3.
Turbine Building Electrical Manhole No. 1 E1, S'-8" 0/2 2/0 l
(located in normal switchgear room)
I
(
4.
Screenwell Pump House Pump Cubicle A 3/0##
Pump Cubicle B 3/0##
5.
Yard l
Emergency Diesel F.O. Transfer Pump l
House A 2/0 Emergency Diesel F.O. Transfer Pump House B 2/0 Emergency Diesel F.O. Transfer Pump House C 2/0 TABLE NOTATIONS
(x/y): x is number of Function A (early warning area fire detection and noti-fication) instruments, y is number of Function B (actuation of fire suppres-sion system and notification) instruments.
~
The fire detection instruments located within the primary containment are not required to be OPERABLE during the performance of Type A Containment Leakage a
Rate Tests.
Heat detectors are non-restorable spot type fixed temperture.
Includesprojectedbeamtypesmokedetector SHOREHAM - UNIT 1 3/4 3-83
.o
' INSTRUMENTATION 1
RADICACTIVE L10VID EFFLUENT MONITORING INSTRUMENTATION i
LIMITING CON 0! TION FOR OPERATION 3.3.7.10 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.10-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded.
The alarm / trip setpoints of these channels shall be determined in accordance with l
the Offsite Dose Calculation Manual (ODCM).
APPLICABILITY:
At all times.
ACTION:
a.
With a radioactive liquid effluent monitoring instrumentation channel alarm / trip setpoint less conservative than required by the above specification, immediately suspend the release of radioactive liquid l
effluents monitored by the affected channel or declare the channel j
inoperable, b.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown j
in Table 3.3.7.10-1.
Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION or explain
(
in the next Semiannual Radioactive Effluent Release Report why this l
inoperability was not corrected within the time specified, c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.7.10.1 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.10-1.
4.3.7.10.2 At least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at least one circulating water pump shall be determined to be operating and providing dilution to the discharge structure whenever dilution is required to meet the site radioactive effluent concentration' limits of Specification 3.11.1.1.
e SHOREHAM - UNIT 1 3/4 3-84 a
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TABLE 3.3.7.10-1 m
h RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUNENTATION e
C3 MINIMUM H
CH4NNELS
~
INSTRUMENT OPERABLE ACTION i
1.
GROSS RADIOACTIVITY MONITORS PROVIDING ALARN AND AUTOMATIC l
TERMINATION OF RELEASE i
a.
Liquid Redwaste Effluent Line, RE-13 1
110 2.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM BUT NOT PROVIDING AUTOM4 TIC TERMINATION OF RELEASE i
a.
RHR Heat Erchanger Service Water Outlet, RE-23A, RE-238 1*
111 I
w f
j g
b.
Reactor Building Salt Water Drain Tank Outlet, RE-79 1
112 l
t 3.
FLOW RATE MEASUREfENT DEVICE a.
Liquid Radwaste Effluent Line 1
113 I
The detector associated with the operating RHR subsystem shall be OPERABLE.
?
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TABLE 3.3.7.10-1 (Continued)
ACTION STATEMENTS ACTION 110 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 14 days p.Tvided that prior to-initiating a release:
a.
At least two independent samples are analyzed in accordance with Specifications 4.11.1.1.1 and 4.11.1.1.2, and b.
At least two technically qualified members of the Station Staff independently verify the release rate calculations and discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
ACTION 111 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, for the detector (s) associated with operating RHR loop (s) effluent releases via the(se) pathway (s) may continue for up to 30 days provided that, t
at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and
,e analyzed for radioactivity at a lower limit of detection of at i
least 10 7 microcurie /mL.
~
ACTION 112 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided that, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , grab samples are collected and analyzed.for radioactivity at a lower limit of detection of at least 10 7 microcurie /mL.
ACTION 113 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via l
this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.
Pump performance curves generated in place may be used to estimate flow.
SHOREHAM - UNIT 1 3/4 3-86
.,.......-.a.
w 5g TABLE 4.3.7.10-1 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLAMCE REQUIRE 9ENTS E
O CHMNEL CHANNEL SOURCE CHANNEL FUNCT10NAL INSTRUMENT CNECK CHECK CALIBRATION TEST 1.
GROSS RADI0 ACTIVITY MONITORS PROVIDING ALARM AND AUTOMATIC TERMINATION OF RELEASE a.
Liquid Radwaste Effluent Line, RE-13 D(4)
P R(3)
Q(1) 2.
GROSS RADI0 ACTIVITY MONITORS R
PROVIDING ALARM 8UT NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE a.
RHR Heat Exchanger Service Water Outlet, RE-23A, RE-238 D
M R(3)
Q(2) b.
Rea: tor Building Salt Water Drain Tank Outlet, RE-79 D
M R(3)
Q(2) 3.
FLOW RATE MEASUREMENT DEVICE a.
Liquid Radwaste Effluent Line D(4)
N.A.
R q
i l
i 7
TABLE 4.3.7.10>1 (Continued)
TABLE NOTATIONS (1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation and/or indication occur if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm / trip setpoint.
2.
Circuit failure; 3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) The CHANNEL FUNCTIONAL 1EST shall also demonstrate that control room alarm annunciation and/or indication occurs if any of the following conditions exists:
1.
Instrument indicates measured levels above the alarm setpoint.
l 2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(3) The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Bureau of Standards (NBS) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall
~
permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have i
j been related to the initial calibration shall be used.
l (4). CHANNEL CHECK shall consist of verifying indication during periods of l
release.
CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days when batch releases are made.
l l
l SHOREHAM - UNIT 1 3/4 3-88 V
l
'].NSTRUMENTATION RADICACTIVE GASEOUS EFFLUENT MON!iORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION l
3.3.7.11 The radioactive gaseous effluent monitoring instrumentation channels shown in '.*able 3.3.7.11-1 shall be OPERABLE with their alarm / trip setpoints set to ensure *. hat the limits of Specification 3.11.2.1 are not exceeded.
The alarm / trip Setpoints of these channels (except hydrogen monitoring) shall be
)
determined in accordance with the ODCM.
APPLICABILITY:
As shown in Table 3.3.7.11-1 ACTION:
5 a.
With a radioactive gaseous effluent monitoring instrumentation channel alarm / trip setpoint less cons,ervative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the affected channel or declare the channel inoperable.
b.
With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.11-1.
Restore the inoperable instrumentation to f
OPERABLE status within the time specified in the ACTION or explain
\\,
in the next Semiannual Radioactive Effluent Release Report why this inoperability was not corrected within the time specified.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
l i
SURVEILLANCE RE001ktMENTS 4.3.7.11 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the
- l frequencies shown in Table 4.3.7.11-1.
i SHOREHAM - UNIT 1 3/4 3-89
E S
TABLE 3.3.7.11-1 G'
E
~ RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION i
e
.c3 MINIMUM CHANNELS
]
INSTRUMENT OPERABLE arrut. ABILITY ACTION 1.
MAIM CONDENSER OFFGAE REATMENT SYSiti4 EFFLUENT MONITORING SYSTEM a.
Noble Gas Activity Monitors - Alam, 1#
120 RE-6SA, RE-658 2.
MAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.
Hydrogen Monitor (downstream of recombiner) 18 121 3.
STATION VENTILATION EXHAUST MONITORING SYSTEM a.
Noble G.s Activity Monitor, RE-42 1
120 b.
Iodine Sample 1
122 c.
Particulate Sampler 1
122 d.
Effluent System Flow Rate Monitor 1
123 e.
Sampler Flow Rate Monitor 1
123 4.
CONDENSER AIR EJECTOR RADIOACTIVITY MONITOR PROVIDING ALARM (TERMINATION OF BYPASS FLOW IS MANUAL) a.
Noble Gas Activity Monitors (prior to input to holdup system), RE-12A. RE-128 If 124 ri.
(
ev
..i i
... - ~ - -,.
TABLE 3.3.7.11-1 (Continued)
TABLE NOTATIONS g
At all times.
During main condenser offgas treatment system operation.
During operation of the main condenser steam jet air ejector (s).
A monitor connected to the operating offgas loop shall be OPERABLE.
ACTION STATEMENTS ACTION 120 -
With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided grab samples are taken at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
ACTION 121 -
With the number of channels OPERABLE less than required by the Minimus Channels OPERABLE requirement, operation of main con-1 i
denser offgas treatment system may continue for up to 30 days provided grab samples are collected at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and analyzed within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
ACTION 122 -
With the number of channels OPERABLE less than required by the
(
Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided samples are continuously collected with auxiliary sampling equipment as required in Table 4.11.2.1.2-1.
ACTION 123 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .
ACTION 124 -
a.
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, the gases from the main condenser may be released to the environment fer up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided:
1.
The offgas system is not bypassed, and 2.
The offgas delay treatment system effluent activity monitor is OPERABLE; Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
b.
With the number of channels OPERABLE equal to the Minimus Channels OPERABLE requirement and the release exceeding the setpoint, terminate the bypass flow manually within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .
1 SHOREHAM - UNIT 1 3/4 3 91
TABLE 4.3.7.11-1 RADIOACTIVE GASEC+Js EFFLUENT MONITORING INSTRUNENTATION SURVEILLANCE REQUIREENTS E
E CMNNEL MODES IN WICM CMNNEL SOURCE CHANNEL FUNCTIOML SURVEILUWm'O.
INSTRUNENT CNECK CHECK CALIBRATION TEST REQUIRED w
w 1.
MAIN CONDENSER OFFGAS TREATENT SYSTEM EFFLUENT MONITORING SYSTEM a.
Noble Gas Activity Monitors -
0 M
R(2)
Q(1)
Alarm, RE-65A, RE-658 2.
MAIN CONDENSER OFFGAS TREATMENT SYSTEM EXPLOSIVE GAS MONITORING SYSTEM a.
Hydrogen Monitor (downstream 0
N.A.
Q(3)
M
,g of recombiner)
T 3.
STATION VENTILATION EXHAUST E
MONITORING SYSTEM a.
Noble Gas Activity Monitor, RE-42 D
M
.R(2)
Q(1) b.
Iodine Sampler W
N.A.
N.A.
N.A.
c.
Particulate Sampler W
N.A.
N.A.
N.A.
d. ~ Effluent System Flow Rate Monitor D
N.A.
Q N.A.
e.
Sampler Flow Rate Monitor D
N.A.
Q N.A.
4.
CONDENSER AIR EJECTOR RADI0 ACTIVITY MONITOR PROVIDING ALAM (TERMINA-TION OF BYPASS FLOW IS MANUAL) a.
Noble Gas Activity Monitors (prior to input to holdup system), RE-12A, RE-128 D
M R(2)
Q(1) 9 s
1 i
s TABLE 4.3.7.11-1 (Continued) i TABLE NOTATIONS
At all times.
During main condenser offgas treatment system operation.
s
During operation of th2 main condenser steam jet air ejector (s),
(1) The CHANNEL FUNCTIONAL TEST shi.11 also demonstrate that control room f
alarm annunciation and/or indie:ation occurs if any of the following condi-tions exists:
1.
Instrument indicates measJred levels above the alarm setpoint.
2.
Circuit failure.
3.
Instrument indicates a downscale failure.
4.
Instrument controls not set in operate mode.
(2) The initial CHANNEL CALIBRATION shall be performed using one or more of
+
the reference standards certified by the National Bureau of Standards (NBS) i or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS.
These standards shall i
\\
permit calibrating the system over its intended range of energy and measurement range.
For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration shall be used.
(3) The CHANNEL CALIBRATION shall include the use of standard gas samples containing a nominal one volume percent hydrogen, balance nitrogen.
i 1
SHOREHAM - UNIT 1 3/4 3-93 l
.=
REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION i
3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.
j APPLICABILITY:
At all times, ACTION:
a.
In OPERATIONAL CONDITION 1:
1.
With the conductivity, chloride concentration, or pH exceeding the limit specified in Table 3.4.4-1 for less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval and, for conductivity and chloride concen-tration, for less than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, but with the conductivity less than 10 pmhos/cm at 25'C and with the chloride concentration l
1ess than 0.5 ppm, this need not be reported to the Commission and the provisions of Specification 3.0.4 are not applicable, 2.
With the conductivity, chloride concentration, or pH exceeding 1
the limit specified in Table 3.4.4-1 for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval or with the conductivity
{
and chloride concentration exceeding the limit specified in Table 3.4.4-1 for more than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, be in at least k
STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .
3.
With the conductivity exceeding 10 pahos/cm at 25'C or chloride concentration exceeding 0.5 ppm, be in at least HOT SHUTDOWN l
within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
l.
b.
In OPERATIONAL CONDITIONS 2 and 3 with the conductivity, chloride l
concentration, or pH exceeding the limit specified in Table 3.4.4-1 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, be in at 1 east HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN l
within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
c.
At all other times: _
i 1.
With the:
a)
Conductivity or pH exceeding the limit specified in Table 3.4.4-1, restore the conductivity and pH to within the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or b)
Chloride concentration exceeding the limit specified in Table 3.4.4-1, restore the chloride concentration to j
within the limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or l
perform an engineering evaluation to determine the effects of the l
out-of-limit condition on the structural integrity of the reactor I
coolant system.
Determine that the structural integrity of the reactor coolant system remains acceptable for continued operation prior to proceeding to OPERATIONAL CONDITION 3.
2.
The provisions of Specification 3.0.3 are not applicable.
SHOREHAM - UNIT 1 3/4 4-13 o
b U
o REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS 4.4.4 The reactor coolant shall be determined to be within the specified chemistry limit by:
a.
Measurement prior to pressurizing the reactor during each startup, if not performed within the previous 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .
b.
Analyzing a Emple of the reactor coolant for:
1.
Chlorides at least once per:
a) 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and b) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months whenever conductivity is greater than the limits in Table 3.4.4-1 l
2.
Conductivity at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .
3.
pH at least once per:
a) 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and b) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months whenever conductivity is greater than the limits f.
in Table 3.4.4-1.
)
s c.
Continuously recording the conductivity of the reactor coolant, or, when the continuous recording conductivity monitor is inoperable, obtaining an in-line conductivity measurement at least once per:
1, 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months in OPERATIONAL i
';0NS 1, 2, and 3, and 2.
24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at all other times, d.
Performance of a CHANNEL CHECK of the continuous conductivity monitor with an in-line flow cell at least once per:
l 1.
7 days, and 2.
24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months whenever conductivity is greatsr than the limits in Table 3.4.4-1.
i h
l SHOREHAM - UNIT 1 3/4 4-14 l
l
C' p
TABLE 3.4.4-1
~ '
o REACTOR COOLANT SYSTEM E
CHEMISTRY LIMITS E
i OPERATIONAL CONDITION CHLORIDES CONDUCTIVITY (puhos/cm 925'C) pH 1
1 0.2 ppe i 1.0 5.6 < pH 1 8.6 2 and 3 10.1 pp:2
< 2.0 5.6 $ pH 1 8.6 i
At aH other times
$ 0.5 ppe
$ 10.0 5.3 $ pH $ 8.6 R.
t:
e r
sp ww-
'W-'
+-
---Y g
v e
p-gyTv==p ew
-NP*-'
.--r-pT e-m y-r e
_a wea
.<y%
v.sy-
CONTAINMENT SYSTEMS REACTOR BUILDING AUTOMATIC ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.5.2 The reactor building ventilation system automatic isolation valves shown in Table 3.6.5.2-1 shall be OPERABLE with isolation times less than or equal to the times shown in Table 3.6.5.2-1.
APPLICABILITY:
OPERATI0NAL CONDITIONS 1, 2, 3, and *.
ACTION:
With one or more of the reactor building ventilation system automatic isolation valves shown in Table 3.6.5.2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either:
t a.
Restore the inoperable valves (s) to OPERABLE status, or b.
Isolate each affected penetration by use of at least one 'feactivated valve secured in the isolation position, or c.
Isolate each affected penetration by use of at least one closed manual valve or blind flange.
1 Otherwise, in OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUT 00WN f
j within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
s Otherwise, in OPERATIONAL CONDITION a, suspend handling of irradiated fuel in i
the secondary containment, CORE ALTERATIONS and operations with a potential
-for draining the reactor vessel.
The provisions of Specification 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS i
4.6.5.2 Each reactor building ventilation system automatic isolation valve shown in Table-3.6.5.2-1 shall be demonstrated OPERABLE:
Prior to returning the valve to service after maintenance, repair, a.
or replacement work is performed on the valve or its associated actuator, control, or power circuit by cycling the valve through at least one complete cycle of full travel and verf fying the specified isolation time.
i l
b.
During COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each isolation L
l valve actuates to its isolation position.
t c.
By verifying the isolation time to be within its limit when tested pursuant to Specification 4.0.5.
When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
SHOREHAM - UNIT 1 3/4 6 38 l
e
+
e g
TABLE 3.6.5.2-1 REACTOR BUILDING VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES MAXIMUM l
ISOLATION TIME VALVE FUNCTION (Seconds) 1.
Reactor Building Normal Ventilation Supply Valve IT46*A0V35A 10 2.
Reactor Building Normal Ventilation l'
Supply Valve IT46*A0V35B 10 3.
Reactor Building Normal Ventilation Exhaust Valve IT46*A0V37A 10 4.
Reactor Building Normal Ventilation Exhaust Valve IT46*A0V376 10 e
r 6
SHOREHAM - UNIT 1 3/4 6-39
o CONTAINMENT SYSTEMS REACTOR BUILDING STANDBY VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.5.3 Two independent reactor building standby ventilation systems (RBSYS) shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, 3, and *.
ACTION:
a.
With one RBSYS inoperable, restore the inoperable system to OPERABLE status within 7 days, or:
1.
In OPERATIONAL CONDITION 1, 2, or 3, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
2.
In OPERATION CONDITION *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
The provisions of Specification 3.0.3 are not applicable.
b.
With both RBSVS inoperable in OPERATIONAL CONDITION
, suspend e
handling of irradiated fuel in the secondary containment, CORE I
ALTERATIONS or optrations with a potential for draining the reactor vessel.
The provisions of Specification 3.0.3, are not applicable.
SURVEILLANCE REQUIREMENTS 4.6.5.3 Each RBSVS shall be demonstrated OPERABLE:
a.
At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters OPERABLE.
i
Wher> irradiated fueFip:being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
SHOREHAM - UNIT 1 3/4 6-40
CONTAINMENT SYSTEMS SURVE!LLANCE REQUIREMENTS (Continued) b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zono communicating with the system by:
1.
Verifying that the system satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 1% and uses the test procedure guidance in Regulatory Positions C.5.a. C.5.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, at a system exhaust flow rate of 1160 cfm 2 10%.
2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52 Revision 2, March 1978, meets the laboratory testing criteria of Regulatory l
Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%; and 3.
Verifying a system exhaust flow rate of 1160 cfm 2 10% during system operation when tested in accordance with ANSI N510-1975.
'l c.
After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying I
within 31 days after removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2. March 1978, meets the laboratory testing criteria of Regulatory Position C.6 a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 1%.
d.
At least once per 18 months by:
1.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber Danks is less than 4.2 inches water gauge while operating the filter train at a system exhaust flow rate of 1160 cfm t 10% in the single train operating mode.
2.
Verifying that the filter train starts and isolation dampers l
open on each of the following test signals:
a.
Manual initiation from the control room, and b.
Simulated automatic initiation signal, 3.
Verifying that the heaters dissipate 5.7 1 1 kW when tested in accordance with ANSI N510-1975.
SHOREHAM - UNIT 1 3/4 6-41
)
l CONTAINMENT $Y$TEMS SURVEILLANCE REQUIREMENTS (Continued) l' e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetra-tion and bypass leakage testing acceptance criteria of less than 1%
in accordance with ANSI N'iO-1975 while operating the system at *a system exhaust flow rate of 1160 cfm i 10% in the single train operating mode.
f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 1% in accordance with ANSI N510-1975 for a halogenated hydrocarbon refrigerant test gas while operating the system at a system exhaust flow rate of 1160 cfm i 10% in the single train oper-ating mode.
t l
1 i
~.
I i
1 1
SHOREHAM - UNIT 1 3/4 6-42
PLANT SYSTEMS l
.3/4.7.7 FIRE SUPPRESSION SYSTEMS J
FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION i
3.7.7.1 The fire suppression water system shall be OPERABLE withi a.
Two OPERABLE fire pumps, one electric motor-driven and one diesel-driven, each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression yard main, b.
Two separate fire water storage tanks, each with a minimum contained volume of 300,000 gallons, and
' i' c.
An OPERABLE flow path capable of taking suction from both of the fire water storage tanks, one at a time, and transferring the water through l
yard main and distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device un each sprinkler or hose stand -
pipe and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.7.7.2, 3.7.7.5, and 3.7.7.6.
s APPLICABILITY:
At all timer.
ACTION:
With one fire pump and/or one water supply inoperable, restore the a.
inoperable equipment to OPERABLE status within 7 days or, provide an alternate backup pump or supply.
The provisions of Specifications
(
3.0.3 and 3.0.4 are not applicable, b.
With the fire suppression water system otherwise inoperable establish a backup fire suppression water system within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREMENTS 4.7.7.1.1 The fire suppression water system shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying the minimum contained water supply volume in each storage tank, b.
At least once per 31 days by starting the electric motor driven fire pump and operating it for at least is minutes on recirculation flow, At least once per 31 days by verifying that each valve (manual, power-c.
operated, or automatic) in the flow path is in its correct position, d.
At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.
SHOREHAM - UNIT 1 3/4 7-22 4
,.e.,,,---.e-e..-
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- - - - ^ ^ - - - - " - - - - -
- - - - - ---~~~~-
+
K' t,
.g NA T SYSTEMS U
SURVEILLANCE REQUIREMENTS (Continued) i e. _.
At least once per 18 months by performing a system functional test which includes simulated automatic actuation of the system throughout its operating sequence, and:
11.
-Verifying that each automatic valve in the flow path actuates o
to its. correct position, 2.
_ Verifying that each fire pump develops at least 2500 gpm at a I
system head of 125 psig.:
I 3.
Cycling each valve _in the flow path thet is-not testable during plant operation through at least one complete cycle of full travel, and
' 4.
Verifying that ce.ch fire pump starts sequentially to maintain the fire suppression water system pressure greater than or equal to.125:psig.-
f._
At least once per 3 years by performing a flow test of the system in' accordance with Chapter 5, Section 11 of the Fire urstection Handbook; 14th Edition, published by the National Fire Protect;en Association.
4.7.7.1.2" The diesel-driven' fire pump shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
3 1.
Verifying the fuel storage tank contains at least 33 inches indicated level (185 gallons) of fuel.
2.
Starting the diesel-driven pump from ambient conditions and operating for greater than or equal'to 30 minutes on recirculation flow, t
b.
At least once per 92 days by verifying that a sample of diesel fuel o
from the fuel storage tank, obtained in accordance with ASTM-D270-75,
'is within the acceptable limits specified in Table 1 of ASTM 0975-77
when checked for viscosity, water, and sociiment.
c.
At least once per 18 months, during shutdown, by subjecting the diesel to an inspection in accordance with procedures prepared in conjunction g
1
'with its manufacturer's recommendations for the class of service.
SHOREHAM - UNIT 1 3/4 7-23
p1
!~
3 3
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
r 4.7.7.1.3 The diesel-driven fire pump starting 24-volt battery bank and g
charger shall be demonstrated OPERA 8LE:
a.
At least' once per 7 days by verifying that:
1.
The electrolyte level of each cell is above the plates, 2.
The cell specific gravity, corrected to 77'F is greater than or
-i equal to 1.250, 3.
The overall battery voltage is greater than or equal to 26.4 volts on float charge.
b.
At least once per 92 days by verifying that the specific gravity is appropriate for continued service of the battery.-
c.
At least once ;,vr 18 month; by verifying that:-
1.
The batteries, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, and 2.
Battery-to-battery and terminal connections are clean, tight, free of corrosion and coated with anticorrosion material.
+
t 6
9 4
SHOREHAM - UNIT 1 3/4 7-24 i
4 e
PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES LIMITING CONDITION FOR OPERATION l
3.7.7.6 The yard' fire hydrants and associated hydrant hose houses shown in Table 3.7.7.6-1 shall be OPERABLE.
APPLICABILITY:
Whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE.
ACTION:
l L
a.
With'one or more of the yard fire hydrants or associated hydrant hose houses shown in Table 3.7.7.6-1 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months i
have sufficient additional lengths of 2 1/2 inch diameter hose located in an adjacent OPERABLE hydrant hose house to provide service to the unprotected areas (s) if the inoperable fire hydrant or associated hydrant hose house is the primary means of the fire.
suppression; otherwise provide the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
b.-
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS l,
4.7.7.6 'Each of the yard fire hy rants and associated hydrant hose houses shown in Table 3.7.7.6-1 shall'be demonstrated OPERABLE:
L a.
-At least once per 31 days by visual inspection of the hydrant hose house to assure all required equipment is at the hose house, b.
At least once per 6 months, during March,-April or May and during September, October or November, by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that-
.the hydrant is not damaged, c.
At least once per 12 months'by:
l 1.
Conducting a hose hydrostatic test at a pressure of 150 psig.or l
at least 50 psig above the maximum fire main operating I
pressure, whichever is greater. -
2.
Replacement of all degraded gaskets in couplings.
3.
Performing a flow chack of each hydrant, k
SHOREHAM - UNIT 1 3/4 7-32
c
,,; E "E
i g
TABLE 3.7.7.6 _1 i
p~'.!:
VARD FIRE' HYDRANTS'AND ASSOCIATE
'i LOCATION:
1
_ HYDRANT NUMBER i:
Near Screenwell end Pump House Nos. 5, 6-Near Control-Building and Diesel Oil Tank-Pump House Nos. 7, 8 and Wall Hydrant
. Reactor Building Nos. 1. 10 t
g.
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L
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t SHOREHAM - UNIT 1 1
3/4 7-33 1
3
.m c
a
PLANT SYSTEMS s
3/4.7.8 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.8 All fire rated assemblies, including walls, floor / ceilings, cable tray enclosures and other fire barriers, separating safety-related fire areas' or separating portions of redundant systems important to safe shutdown within a fire area, and all sealing devices in fire rated assembly penetrations, including fire doors, fire windows, fire dampers, cable and piping penetra-3 tion seals and ventilation seals, shall be OPERABLE.
APPLICABILITY:
At all times.
ACTION:
i a.
With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch on at-least one side of the affected assembly (s) and/or sealing device (s) or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly (s) and sealing device (s) and establish an hourly fire watch patrol.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable..
SURVEILLANCE REQUIREMENTS
4. 7. 6.1 Each of the above required fire rated assemblies and penetration sealing devices shall be verified OPERABLE at least once per 18 months by performing a visual inspection of:
a.
The exposed surfaces of each fire rated assembly, b.
Each fire window, fire damper, and associated hardware.
l c.
At least 10% of each type of sealed penetration.
If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10% of each type of sealed penettstion l
shall be made.
This inspection process shall continue until a 10%
sample with no. apparent changes in appearance or abnormal degradation is found.
Samples shall be selected such that each penetration seal will be inspected at least once per 15 years.
4.7.8.2 Each of the above required fire doors shall be verified OPERABLE by inspecting the latches at least once per 6 months, and by verifying:
a.
The OPERABILITY of the fire door supervision system for each electri-cally supervised fire door by performing a CHANNEL FUNCTIONAL TEST h
I at least once per 31 days.
5 SHOREHAM - UNIT 3 3/4 7-34 1
I u
PLANT SYSTEMS 3/4.7.9 AREA TEMPERATURE MONITORING LIMITING CONDITION FOR OPERATION o
3.7.9 The temperature of each area shown in Table 3.7.9-1 shall be mair.tained within the limits indicated.
APPLICABILITY:
Whenever-the equipment in an affected area is required to be
~
OPERABLE.
ACTION:
With one or pare areas exceeding the temperature limit (s) shown in Table 3.7.9-1:
l s
a.
For more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , in lieu of any report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days providing a record of the amount by which and the cumulative time the temperature in the affected area exceeded its limit and an analysis to demonstrate the continued OPERABILITY of the affected equipment.
b.
_By more than 30*F, in addition to the Special-Report required above.
within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area to within its temperature c
limit or declare the equipment in-the affected area inoperable, l
SURVEILLANCE REQUIREMENTS 4.7.9 The temperature in each of the areas shown in Table 3.7.9-1 shall be determined to be within its limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
l l
SHOREHAM - UNIT 1 3/4 7-36 l
i c-TABLE 3.7.9-1
'. (,
AREA TEMPERATURE MONITORING
- l AREA TEMPERATURE LIMIT (*F)-
a.
Control Room 90 b.
Chiller Equipment Room (El 63')
104 c.
-Relay' Room 104 d.
Emergency Switchgear-Rooms 104 I
e.
Battery Rooms 104
f..
Diesel Generator Rooms 120 g.
Screenwell House 104 h.
Reactor Building - Secondary Containment L
1.. General Areas 104 2.
Refueling Area 110 1.
Reactor Building - Primary Containment 1.
General Areas 150 u 1 (1 2.
Area Beneath RPV.
.150*
-3.
Drywell Head Area
.185-
[
'1 l
R165'F during Scram.
l SHOREHAM - UNIT 1 3/4 7-37
tr ' 1 9'
.s
~3/4.11 RADI0 ACTIVE EFFLUENTS 4
3/4.11.1 LIQUID EFFLUENTS CONCENTRATION ~
]
LIMITING CON 0! TION FOR OPERATION 3.11.1.1 The concentration of radioactive material released in liquid effluents-to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited to the concentrations.
specified in 10 OCR Part 20. Appendix 8. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases.
For dissolved or entrained noble I
gases, the concentration shall be limited to 2 x.10 4 microcurie /mL total activity.
APPLICABILITY:
At all times.
i
^
ACTION:
4 With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immediately restore the con j centration to within the above limits.
i l
SURVEILLANCE REQUIREMENTS -4.11.1.1.1 Radioactive liquid wastes shall be sampled and analyzed according to the sampling and analysis program of Table.4.11.1.1.1-1.
4.11.1.1.2 The results of the radioactivity analyses shall be used in accord-
-ance with the methodology and parameters in the ODCM to assure that the u
L
-concentrations at the point of release are maintained within the limits of Specification 3.11.1.1.
t I-l' O
l SHOREHAM - UNIT 1 3/4 11-1
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-TABLE 4.11.1,1.1-1 o
RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum Type of of Detection i
' Liquid Release Sampling Analysis Activity (LLD) l 3;-
Type Frequency Frequency Analysis (pCi/mL)*
~7
-A; Batch Waste P
P Principa} Gamma 5x10 ReleaseTagks Each Batch Each Ba'.ch Emitters and Sumps
-6
1. Discharge I-131 1x10
-Waste Sample
-5 Tanks P*
M*
Dissolved and 1x10 L
One Batch /M Entrained Gases 2'.
Recovery (Gamma Emitters) i_
Sample Tanks
-5 p
g H-3 1x10 d
Fach Batch Composite 7
Gross Alpha 1x10 l
1
3. Yard Pip-
-8 ing Drain P
Q Sr-89, Sr-90 5x10
'~
d Sump Each Batch Composite
-6 l-Fe-55 1x10 y
~7 l l-B. Continuogs
'O W
Principa} Gamma 5x10 d
Releases Grab Sample' Composite Emitters gs
1. RHR Heat
-6 Exchanger I-131 1x10 Service
-5
. Water M
M Dissolved and 1x10 I' '
Outlet Grab Sample Entrained Gases l
(GammaEmitters)
2. Reactor
-Building
-5 Salt Water D
M H-3 1x10 d
Drain Tank Grab Sample Composite g
7 l
Gross Alpha 1x10 p[
0 Q
Sr-89, Sr-90 5x10~8 d
Grab Sample Composite
-6 Fe-55 1x10
If a batch is released during the month.
'SHOREHAM - UNIT 1 3/4 11-2
TABLE 4.11.1.1.1-1 (Continued)
TABLE NOTATION aThe LLD is-de ined, for purposes of these specifications as the smallest concentration (ofradioactivematerialinasamplethatwlliyieldanet with only 5% p'ystem background, that will be detected with 95% proba count, above s robability of falsely concluding that a blank observation represents a real" signal.
For a particular measurement system, which may include radiochemical separation:
4.66 s b LLD =
E V
2.22 x 10" Y
exp (-Aot)
(
-Where:
LLD is the "a priori" lower limit of detecti6n as defined above, as microcuries per unit mass or volume, s
is the standard deviation of the background counting rate or of thecountingrateofablank.sampleasappropriate,ascountspera
minute, E is the counting efficiency, as coun" per disintegration, l
V is the sample s'ize in units of mt-or volume,
'2.22 x 105 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the-radioactive decay constant.for the particular radionuclide, -
and at for plant effluents is the elapsed time between the midpoint of sample collection and the time of counting.
l-Typical values of E, V, Y, and at should be used in the calculation.
l l
It should be recognized that.the LLD is defined as an a. priori-(before the L
. fact) limit representing the capability of the measureiiient system and not as a posteriori (after the fact) limit for a particular measurement, bA batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed by a method described in the ODCM to assure representative sampling.
SHOREHAM - UNIT 1 3/4 11-3
vn hi
^
TABLE 4.11.1.1.1-1 (Continued)
\\
TABLE NOTATIONS (Continued) l cThe principal gamma emitters for which the LLD specification applies include L
the following radionuclides:
Mn-54, Fe-59, Co-58 Co-60, Zn-65, Mo-99, C's-134, p
Cs-137, Co-141, and Ce-144.
This list does not mean that only these nuclides H
are to be considered.
Other gamma peaks that are identifiable, together with j
those of the above nuclides, shall also be analyzed and reported in the Semi-1 annual Radioactive Effluent Release Report pursuant to Specification 6.9.1.7.
1 L
dA composite sample is one in which the quantity of liquid sarespied is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that-is representative of the liquids released.
'A continuous release is the discharge of liquid wastes of a nondiscrete volume, e.g.,' from a volume of a system that has an input flow during the v
continuous release.
..I u
SHOREHAM - UNIT 1 3/4 11-4
1
,=
RADI0 ACTIVE EFFLUENTS
' DOSE g;
LIMITING CONDITION FOR OPERATION R
1 3.11.1.2' The dose or dose commitment to a MEMBER OF THE PUBLIC from
~
radioactive materials in liquid effluents released, from each reactor unit, to
-UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited:
l a.
During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and-b.
During any calendar year to less than.or equal to 3 mrems to the total body and to-less than or equal to 10 mrems to any organ.
APPLICABILITY:
At all times.
ACTION:
a.
With the calculated dose from the release of radioactive materials in liquid effluents-exceeding any of the above limits prepare and-submit to the Commission within 30 days, pursuant to Specifica-L tion 6.9.2, a-Special Report that identifies the cause(s) for exceeding y the limit (s) and defines the corrective actions that have been taken to f
.[- ~
reduce the releases and the proposed corrective actions to be taken to L\\
assure that subsequent releases will be in compliance with the above limits.
1 L.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.11.1.2-Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in
.accordance with the methodology and parameters in the 00CM at least once per l
31 days.
L L
SHOREHAM - UNIT'1 3/4 11-5
a RADIOACTIVE EFFLUENTS LIQUID-RADWASTE TREATMENT SYSTEM.
-LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appro-priate portions of the system shall be used to reduce releases of radioactivity when the projected doses due to the liquid effluent, from each reactor unit-to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.06 mrem to the total body' or 0.2 mrem to any organs in a 31-day period.
APDLICABILITY:
At all times.
ACTION:
With radioactive liquid waste being discharged,without treatment and-a.
in excess of the above limits and any portion of the liquid radwaste treatment system not in operation, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:
1.
Explanation of why liquid radwaste was being discharged without; treatment, identification of any inoperable equipment or subsystems, and the reason for the inoperability.
2.
Action (s) taken to restore the inoperable equipment to OPERABLE status, and 3.
Summary description of action (s) taken to prevent a recurrence.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE' REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to UNRESTRICTED AREAS shall be
. projected at least once per 31 days, in accordance with the methodology and parameters in the 00CM.
.4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by treeting Specifications 3.11.1.1 and 3.11.1.2.
Sh.56 HAM - UNIT 1 3/4 11-6
09 E
RADIOACTIVE EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in each outside-temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.
APPLICABILITY:
At all times.
ACTION:
a.
With the quantity of radioactive material in any outside temporary tank exceeding the above limit, immediately suspend all additions of.
radioactive material to the tank and within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank'
' contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent-Release Report.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
V
(
SURVEILLANCE REQUIREMENTS
'4.11.1.4 The quantity of radioactive material contained in each outside temporary tank shall be determined to be within the above limit by analyzing a representative. sample of the tank's contents at least once per 7 days when.
radioactive materials are~being added to the tank.
U L
t SHOREHAM - UNIT 1 3/4 11-7 1'
'.'RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLIO RADIOACTIVE WASTE LIMITING CONDITION FOR OPERATION' 3.11.3 Radioactive wastes shall be SOLIDIFIED or dewatered in accordance with Y
the PROCESS CONTROL PROGRAM to meet shipping and transportation requirements during transit, and disposal site requirements when received at the disposa'l
site, APPLICABILITY:
At all times.
ACTION:
With SOLIDIFICATION or dewatering not meeting disposal site and a.
shipping and transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures, and/or the solid waste system as necessary to prevent recurrence, b.
With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, (1) test the improperly processed waste in each container to ensure that it meets burial ground and shipping requirements and (2) take appropriate administrative action to prevent; recurrence,
'The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
.-SURVEILLANCE REQUIREMENTS 4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive wastes (e.g., filter sludges, spent resins, evaporator bottoms, boric acid solutions, and sodium sulfate solutions) shall be verified in accordance with the PROCESS CONTROL PROGRAM.
t If any test specimen fails to verify SOLIDIFICATION, the SOLIDIFICATION a.
of the batch under test'shall be suspended until such time as addi-tional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION. _SOLIDIFI-CATION of the batch may then be resumed using the altercative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.
b.
If the initial test. specimen from a batch af waste fails to verify SOLIDIFICATION, the PROCESS CONTROL PROGRAM shall provide for the collection and testing of representative test' specimens from each consecutive batch of the same. type of wet waste until at least three consecutive initial test specimens demonstrate SOLIDIFICATION.
The PROCESS CONTROL PROGRAM shall be modified as required, as provided in Specification 6.13, to assure SOLIDIFICATION of subsequent batches of waste, With the installed equipment incapable of meeting Specification 3.11.3 c.
l or declared inoperable, restore the equipment to OPERABLE status or g
L provide for contract capability to process wastes as necessary to y
satisfy all applicable transportation and disposal requirements.
SHOREHAM - UNIT 1 3/4 11-20
nh
~
,j I,
3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING g
I 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION t
3.12.1 The radiological environmental monitoring program shall be conducted as specified in Table 3.12.1-1.
APPLICABILITY:
At all times.
ACTION:
a.
With the radiological environmental monitoring program not being con-ducted as specified in Table 3.12.1-1, prepare and submit to the Commission, in the Annual Radiological Environmental Operating Report required by Specification 6.9.1.6, a description of the reasons for not conducting the program as required and the plans for preventing.
a recurrence, b.
With the level of radioactivity as the result of plant effluents in.
anenvironmentalsamplingmediumataspecifiedlocationexceedingdar the reporting levels of Table 3.12.1-2 when averaged over any cale quarter, prepare and submit to the Commission, within 30 days,-pure suant to Specification 6.9.2, a Special Report that identifies thei cause(s) for exceeding the limit (s) and defines the corrective actions I
to be taken to reduce radioactive effluents so that the potential
. h1 annual dose
to A MEMBER OF THE PUBLIC is less than the calendar year-limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3.
When more than one of the radionuclides in Table 3.12.1-2 are detected in the
')
sampling medium, this report shall be submittea if:
concentration (1) concentration (2)
+ ***> 1.0 reporting level (1) reporting levei (2)
When radionuclides other than those in Table 3.12.1-2 are detected:
and are the result of plant effluents, this report shall be submitted if the. potential annual-dose
to-A MEMBER OF THE PUBLIC is equal to or greater than the calendar year limits of Specifications 3.11.1.2, 3.11.2.2, and 3.11.2.3.
This report-is not' required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in
,j the Annual Radiological Environmental Operating Report.
The methodology and parameters used to estimate the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.
/SHOREHAM - UNIT 1 3/4 12-1
.~
RAL10 LOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued)
-ACTION:
(Continued)~
With milk or. fresh. leafy vegetable samples discontinued from one or c.
more of the sample locations required by Table 3.12.1-1, identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 days.
The i
specific-locations from which samples were unavailable may then be deleted from the 'nonitoring program.
Pursuant to Specification 6.9.1.7, identify the cause of the unavailability of samples and identify the new locations (s) for obtaining replacement samples in the next Semi-annual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the 00CM reflecting the new locations (s).
d.
The provisions of Specifications 3.0.3 and 3.0.4 are.not applicable.
SURVEILLANCE R'EQUIREMENTS
-4.12.1. The radiological environmental-monitoring samples shall be collected 4 pursuant-to Table 3.12.1-1 from the specific locations given in the table and figures in the ODCM, and-shall be analyzed pursuant to the requirement of
. Table 3.12.1-1 and the detection capabilities required by 4.12.1-1.
i i i
l
]
I L
l l'
h L
~SHOREHAM - UNIT 1 3/4 12-2 L
_S..:
~
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l.
.c.
+
=
' TABLE 3.12.1-1 sg o
RADIOLOGICAL ENVIRONDENTAL MDNITORING PROGRAM *
=
mx E
EXF050RE PATHWAY NUfBER.0F REPRESENTATIVE:
SAMPLING AfW TYPE Afe FREQUENCY y.AND/OR SAMPLE SAMPLES ADO SAMPLE LOCATION COLLECTION FREQUENCY OF ANALYSIS 8
h
1. DIRECT RADIATION 36 routine monitoring stations,-
Quarterly.
Camma dose quarterly.
DR1-DR36, either with two or more dosimeters or with one instrument for measuring and recording dose rate continuously, placed as follows:-
a. An inner ring of stations, one in each meteorological sector in the general' area of the SITE BOUNDARY, DRL-DR16;
[
b. An outer ring of stations, one in
}
each meteorological sector in the 6.to 8-km range from the site,
~?
DR17-DR25;
c. The balance of the stations, DR26-DR36, to be placed in special: interest areas such as-population centers,inearby residences, schools, and in 1 or 2 areas to serve as control stations.
i aber, media, frequency, and location of.. samples may vary from site to site.
This table presents an
a aptable minimum program for a site'at which each entry is applicable.
Local site characteristics must
n. wined to determine if pathways not-covered by this. table may significantly contribute to an indi-'
+!v1's dose ar.d should be included in the sampling program.
.e k
u.
u
_ i TABLE 3.12.1-1 (Continued)
E S
RADIOLOGICAL ENVIR0000 ENTAL MONITORING PROGRAM 2
$ EXPOSURE PATHWAY NUISER OF REPRESENTATIVES SAMPLING AND TYPE AND FREQUENCY' AND/OR SAMPLE SAMPLES AND' SAMPLE ~ LOCATIONS
COLLECTION FREQUENCY OF ANALYSIS
_E 2. AIRBORNE.
Radioiodine and
-Samples from 5 locations, Al-AS:
Continuous sampler Radiciodine Cannister:
Particulates operation with sample I-131 analysis weekly.
3 samples,'Al-A3* from close collection weekly, or
-to the 3 SITE BOUNDARY locations, more frequently if in different sectors, of the required by dust Particulate Sampler:
l highest calculated annual average loading.
groundlevel.D/Q.
Gross beta radioactivity analysis folleging filter change; Gy 1 sample, A4, from the vicinity isotopic analysis of a community having the highest of composite (by calculated annual average groundlevel l,
w1 D/Q.
location) quarterly.
l "7
1 sample, A5, from a control location, 3'
as for example 15-30 km distant and in the least prevalent wind direction.'
3. WATERBORNE
a. Surface 1 sample control, Wal Grab sample semi-Gamma isotopic analysis' (Long Island I sample discharge, Wa2 or Wa3 annually.
and tritium analysis Sound)
-semiannually.
b. Ground Samples from 1 or 2 sources, Wbl, Quarterly.
Gamma isotopic' and Wb2,.only if likely to be affected.7
' tritium analysis quarterly.
c. Sediment from I sample from downstream area with Semiannually.
Gamma isotopic analysis' shoreline existing or potential recreational value, Wdl.
semiannually.
The first and second highest D/Q sectors have radioiodine and particulate samples.
sector at the SITE BOUNDARY is approximately 150 ft from the first highest sector.
The third highest D/Q 7
y
a
' ' ' ' ' ~
~ ~~
3;~} >
7,
~
j TABLE 3.12.1-1 (Continued)
RADIOLOGICAL ENVIR00 MENTAL MONITORING PROGRAM b
EXPOSURE PATHWAY if NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND FREQUENCY 8
AND/0R SAMPLE SAMPLES AND-SAMPLE LOCATIONS COLLECTION FREQUENCY
' 0F ANALYSIS' E
4. INGESTION
a. Milk Samples from milking animals in Semimonthly when GammaisotopicIand1-131' location, Ial, within 5 km distance animals are on analysis seminenthly when.
- having the highest dose potential.
pasture, monthly at animals are on pasture;
' If there are none, then, 1 sample other times.
- monthly at other times.
from milking animals in each of 3 areas, Ial, between 5 to 8 km distant where doses are calculated to be greater than 1 arem per yr, or if there are none available
{
within8km,thenalocatiog8to 17 km distant will be used.
y 1 sample from milking animi1s at a control location, Ia2, 15-30 km w
distant, and not in a direction prevalently downwind from the Plant.
b. Fish and 1 sample of each commercially and Sample in season Gamma isotopic analysis' Invertebrates recreationally important species in or semiannually
.on edible portions.
- vicinity of plant discharge area, if they are not Ib1 - Ib2.
seasonal.
1-sample of same species in areas not influenced by plant discharge, Ib3.
c. Food Products Samples of 3 different kinds of broad At_ time of harvest.I Gamma isotopic' and I-131' leaf vegetation grown nearest each of analysis.
two different offsite locations of highest predicted annual average ground-level D/Q, if milk sampling. is not performed, Ic1 - Ic3.
1
-1 sample of each of the similar broad At time of harvest.'
Gamma isotopic' and I-131 leaf vegetation grown 15-30 km distant
- analysis.
in the least prevalent-wind direction if milk sampling is not perform, Ic3.
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TABLE NOTATIONS
Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, are provided for each and every sample location in Table 3.12.1-1 in a table and figure in the CDCM.
Refer to NUREG-0133, " Preparation of Radiological Effluent Technical Specif1-cations for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch-Technical Position, Revision 1. November 1979.
Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment, and other legitimate reasons.
If specimens are unobtain-able due to sampling equipment malfunction, every effort shall be made to com-plete corrective action prior to the end of the next sampling period.
All deviations from the sampling schedule shall be documented in the Annual Radio-logical Environmenta'l Operating Report pursuant to Specification 6.9.1.6.
It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most' desired location or time.
In these instances suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within L
30 days in the radiological environmental monitoring program.
Pursuant to Specification 6.9.1.7, identify the cause of the unavailability of samples for that pathway and identify t,he new location (s) for-obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report and also include in the report a' revised figure (s) and table for the ODCM reflecting the new location (s).
L h
one or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, s
integrating dosimeters.- For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one phosphor; two or more phosphors in a packet are considered as two or more dosimeters.
Film. badges shall not be used as dosimeters for measuring direct radiation.
The frequency of analysis or readout for TLD systems will depend upon.the characteristics of the specific L
system used and should be selected to obtain optimum dose information with minimal fading.
CThe purpose of this sample is to obtain background information. If it is not i
practical to establish control locations in accordance with the distance and-wind direction criteria, other sites that provide valid background' data may be suostituted, dAirborne particulate sample filters shall be analyzed for gross beta radio-i activity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thoron daughter decay.
If gross beta activity.in air particulate samples is greater than 10 times the yearly mean of control samples, gamma isotopic analysis shall be L
performed on-the individual samples, 1
' Gamma' isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the
~ facility.
SHOREHAM - UNIT 1 3/4 12-6
r; 1
TABLE 3.12.1-1 (Continued)
TABLE NOTATIONS (Continued)
IGroundwater samples shall be taken when this source is-tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge proper-ties are suitable for contamination.
9The. dose shall be calculated for the maximum organ and age group, using the
[
methodology.and parameters in the ODCM.
hThe " control" sample shall be taken at a distance beyond significant influence of the discharge.
The " discharge" sample shall be taken in an area beyond but near the mixing zone.
I If harvest occurs more than once a year, sampling shall be performed during each discrete harvest.
If harvest occurs continuously, sampling shall be monthly.
Attention shall be paid to including samples of tuberous and root food products.
5
. SHOREHAM - UNIT 1 3/4 12-7
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REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIROW4 ENTAL SAMPLES f
Reporting Levels z
WATER AIRBORNE PARTICULATE FISH
-MILK
' FOOD PRODUCTS.
a ANALYSIS (pCi/L)
OR GASES (pci/m ).
(pci/kg, wet)
-(pci/L)
(pci/kg,' wet) _
H-3 30,000 Mn-54 1,000 30,000 Fe-59 400 10,000 w
A Co-58 1,000 30,000 T
Co-60 300 10,000 co Zn-65
~300 20,000 Zr-Nb-95 400 I-131 2
0.9 3
100 Cs-134 30-10 1,000 60 1,000 i
Cs-137 50 20 2,000 70 2,000 Ba-La-140 200 300 I
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DETECTION CAPABILIUFS 'FOR ENVIROMENTAL SAMPLE ANALYSISab LOWER' LIMIT OF DETECTION-(LLD)C
-5
-4 H
- AIRBORNE PARTICULATE WATER OR GAS'-
FISH.
MILK
' FOOD PRODUCTS-
SEDIMENTS ANALYSIS (pCi/L)
-(pCi/m )
(pCi/kg, wet)-
(pCi/L)
(pci/kg, wet)
(pci/kg,' dry) 8 Gross Beta 4
0.01 H-3 3000 Mn-54 15 130 l
Fe-59 30 260 Co-58, 60 15
.130 2n-65 30 260 i
g 7
Zr-95 30 i
Nb-95 15 d-I-131 I
0.07~
1 60 Cs-134 15 0.05 130 15 60 150 Cs-137
.18 0.06 150 18 80 180 Ba-140 60 60.
La-140 15 15
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TABLE 4.12.1-1 (Continued)
TABLE NOTATIONS
- "This. list does not mean tnat only these nuclides are to be considered.
Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.6.
Required detection capabilities for thermoluminescent dosimeterb used for environmental measurements are given in Regulatory Guide 4.13.
cThe LLD is defined, the purposes of these specifications, as the smallest con-centration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.
For a particular measurement system, which may include radiochemical separation:
LLD =
4.66 s b E. V. 2.22. Y. exp (-Aat) i-Where:
j LLD is the "a priori" lower limit of detection as defined above, as picocurie per unit mass or volume, is the standard deviation of the background counting rate or of sb tne counting rate of a blank sample as appropriate, as counts per j
-minute, i
E is the counting efficiency (as counts per transformation).
V is the sample size in units of mass or volume, 2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and at for environmental sampler is the elapsed time between sample ~
collection, or end of the semple collection period, and time of counting.
Typical values of E, V, Y, and at shall be used in the calculations.
l SHOREHAM - UNIT 1 3/4 12-10 1
TABLE 4.12.1-1 (Continued)
TABLE NOTATIO'NS (Continued)
It should be' recognized that the LLD is dsfined as an a priori (before the fact) limit representing the capability o' a measuremelit system and not as an a posteriori (after the fact) limit fot'a particular measurement.-
Analyses shat 1 be performed in such a manner that tne st.ated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interferring nuclides, or other uncon-trollable circumstances may render these LLDs unachievable.
In such cases, j
the contributing-factors shall be identified and described in the Annual Radiological Environmental Operating Report purusant to Specification 6.9.1.6.
dLLD for drinking water samples.
If no drinking water pathway exists, the LLD of gamma isotopic analysis may be used.
1
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SHOREHAM - UNIT 1 3/4 12-11
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l-SECTION 5.0 DESIGN' FEATURES
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I ADMINISTRATIVE CONTROLS F
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I 6.0 ADMINISTRATIVE CONTROLS
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6.1 RESPONSIBILITY Ahe&f
)h hall delegate in writing the succession to this,,overall k,o,p
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The Plant Manager shtil be responsible fot 6.1.1 responsibility during and his beence &.W '"
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Q; The;;;.:t:fonshiftshallbdr9spons[b for the plant,a.~......
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/g, i 6.2 CRGAN!!ATION v$r
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6.2.1 Nuclear crosnisation An organlaation shall be established for unit otosatson and corporate f
Thisorganizationshallincludethepositionsforactivities;d,]
e l management.
plant, y Ky c/ 4.4,L'A/~.A p af_fecting the ::fety ;f th:
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Lines of authority, responsibility and communication shall be-established and defined from the highest management levels
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threueh intermediate 1_evels to and including all ;;; n tir;
'.A M eanizationp positions?
These relationships shall be documented
/
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and updated, as appropriate, in the form of creanizational
y )f charts, functional descriptions of departmental responsibilities
.A and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These
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requirements shall be dccumented in the SAR and updated in
't accordance with 10 CFR 50.71(a).
Y' b.
The responsible Vice President shall have corporate responsibility for overall plant nuclear safety and shall take f
any. measures needed to ensure acceptable performance of the staff in operating, maintaining, and pr vidi.ng technipal s tg the p.'. ant. to ensure
1.... ;tys *. f 4h p %
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c.
The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities neces g gitpr afe ;;..i.1;; ;;i maintenance of the Nant-/E,9 d.
The individials who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organisation;* freedom to ensure their independence from operating pressures.
SHOREMAM - UNIT 1 6-1
4 j
ADMINISTRATIVE CONTROLS l
UNIT STAFF 6.2.2 The station organisation shall be emb(xt "
fell a.
Each duty shift shall be compos 6d of at eggt knia hift "A+
W d
cbsw consist,ing/A>3of th,reat operators e 251: :'h,TV spondM 4 /,,, %
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b.
At st onttoperator who is qualif any alas..s that may occur ch::10... m.lir be in the Control
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Roomwhenfuelisinthespent,FuelP,oo{
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All fuerh'andiina operations shall bef observed and directly c.
supervised by a licensed operator or individual licensed to s~pervise the handline of irradiated fuel, and who has no other encurrent responsibilities during this operation 4 W i
Adequate shift coverase shall be maintained without routine heavy use of overtime.
The ob4ective shall be to have operating personnel work a normal I-hour day, 40-hour week.
However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of fuel movement, major maintenance, or major unit modification, on a temporary i
basis the following auidelines shall be ic11 owed:
1.
An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time.
2.
An individual should not be permitted to work more than 16 f
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, all excluding shift turnov6e time.
3.
A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months shou 2d be allowed between work periods. including shift turnover time.
Any deviation from the above guidlines shall be authorised by the Plant t
Manager or his deputy, or higher levels of management.
l 6.3 UNIT STATT OUALITICATIONS l'
i 6.3.1 rach member of the unit staff shall meet or exceed the minimum Gni.ivn d-W+ % ' ^
i r s-' i,reesh. as units..; au
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qualifications of-Me - i.:
Dedus ed-safety-Anarlyste-Report-fo:
M Geneuct
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l SHOREHAM - UNIT 1 6-2 L
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. ADMINISTRATIVE CONTROLS l
1 6.4 TRAINING
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6.4.1 A retrainine and replacement training program for the station staff
]
shall be maintained under the direction of the Training Supervisor, shall neet.or exceed the requirements of e-progsans-end-psoceamses as.eutMnee een-Sec'Et'5ff~27.-2-eTraining Progt
, of-ths.Def,veled Safety-Anebye6 e ;- %
i N* A//f7 // /P. / ' N 7/,
1 6.s arv2rw AND AvorT 6.5.1 Rrvitw or oPERATroNS COMMITTEE g 4
IB$112!!
6.5.1.1 The ROC shall function to advise the Plant Manaser en all matters q
related to nuclear safaty.
4 COMPMJTION 6.5.1.2 The Roc shall be composed of a chairman or alternate chairman and four members or alternate members of the Plant staff as desionated by the-chairman.
l l
ALTERNATES 6.5.1.3 All alternate members shall be appointed in writino by the Roc Chairmant however, no more than one alternate shall participate as a voting member in DOC activities at any one time.
MttTING FRr0UENCY i
6.5.1.4 The ROC shall meet it.least once per calendar month and as convened by the ROC Chairman or his desionated alternate.
i m
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I 4
9 SHOREMAM - UNIT 1 6-3 1
4 N
' ADMINISTRATIVE CONTROLS 2222E5 6.5.1.5 The quorum of the ROC necessary for the p rformance of the Roc
]
responsibility and authority provisions of these Technical specifications l
ahall consist of the Chairm.an or hi; feri;n tre alternate and two other membirs including alternates.
jf,
1
^ ~ * ' ' '
RESPON8!BIL772E8 6.5.1.6 The ROC shall be responsible for a.
Review of (1) all proposed procedures reqaired 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 changes thereto as determined by the Plant Manager to affect n9 clear safety; i
b.
Review of all proposed tests and experiments that affect nuclear safety; c.
Review of all proposed changes to Appendix A Technical j
specifications; d.
Review of eli proposed chances or modifications to unit systems or equipment that affect nuclear safety; e.
Investination of all violations of the Technical specifications, includina the preparation and forwardina of reports covering evaluation and recommendations to prevent recurrence, to the
. responsible Vice Presidents f.
Review of all REPORTABLE EVENTS; i
c.
Review of station operations to detect potential hasards to nuclear safety; h.
Performance of special reviews, investications, or analyses and reports thereon as requested by the Plant Manager; i.
Review of the security Plan and implementing procedures; j.
Review of the Emergency Plan and implementing procedures; k.
Review of the Firs Protection Plan and implementing procedures; l.
l l
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suonraxx - cxzT 1 6-4
]
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i e
ADMINISTRATIVE CONTROLS
. 1 1.
Review of the proposed changes to the Process control Program (PCP) m.
Review of the proposed changes to the offsite Dose calculation Manual (ODcN) n.
Review of the proposed Major Changes to Radioactive Waste 4
systems; o.
Review of Personnel Radiation Records annually to determine how exposures might be lowered consistent with ALARA principles.
Document such considerationst 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 i
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 j
of items considered under specification 6.5.1.6a. through d. and
n. prier to their implementation.
i I
b.
Render determinations in writing with regard to whether or not each item considered-under Specification 6.5.1.6a. throuch e.
i 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 Manaaer; however, the Plant Manaaer shall have responsibility for resolution of such disagreements pursuant to specification 6.1.1.
9 RECORDS
\\
6.5.1.0 The ROC shall maintain written minutes of each Roc meeting that, at a minimum, document the results of all Roc activities performed under the responsibility provisions of these Technical specifipations.
copies shall be provided to the responsible Vice President W,tO g Q,
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e 1
e SHOREHAM - UNIT 1 6-5
A_m!N!BTRATIVE CONTROLS 6.5.2 NUCLEAR REVIEW 30ARD (NRB) l 71MCTION I
l 6.5.2.1 The NRs shall function to provide independent review and audit of L
designated activities in the areas'of s.
Nuclear engineering, b.
Chemistry and radiochemistry, c.
Radiological safety, d.
Mechanical and electrical engineering, and e.
Quality assurance practices.
The NRB shall report to and advise the Assistant Vice President - Nuclear operations on those areas of responsibility in specifications 6.5.2.7 and 6.5.2.0.
COMP 0 FIT 20N 6.5.2.2 The NRB shall be composed of the permanent NRS Chairman and a i
minimum of four permanent NRB members.
The chairman and all members of the 1
NRB shall have qualifications that meet the requirements of Section 4.7 of ANSI /ANS 3.1-1978.
The membership shall include at least one individual from outside LILC0's or its contractors' organizations and at least one individual with substan-tial nuclear experience.
The nuclear experience may be provided by the individual who is from outside LILCO's or its contractors' organisations.
ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NRS Chairman to serve on a temporary basis; however, no more than enNr 05cA
'alternatep shall participate as votina members in NRB activities at any one time.
CONSULTANTS 6.5.2.4 Consultants shall be utill ed as determined by the NRB Chairman to provide expert advice to the NRB.
MEETING FREQUENCY 6.5.2.5 The NRB shall meet at least once per six months.
SHORIHAM - UNIT 1 6-6 p.g.,,_
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l ADMINISTRATIVE CONTROLS I
EESIE1 6.5.2.6 The quorum of the NRB necessary for the performance of the WRB review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least three but not less than one-half of the NRB members present including alternates.
No more than a minority of the querum shall have line responsibility for operation of the unit.
l l'S h Ama 6.5.2.7 The NRB shall review l
a.
The safet evaluations for (1) changes to equipment or systems and (2) sts or experiments completed under the provision of 10 CFR 50.
to verify that such actions did not consititute an unreviewed safety question; b.
Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59 c.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59; d.
Preposed changes to Technical Specifications or this operatina License; e.
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions havina nuclear safety significance; f.
Stanificant deviations from normal and expected performance of c
station equipment that affect nuclear safety:
c.
All REPORTABLE EVf.NTS; h.
All recoonized indications of an unanticipated deficiency in some aspect of design or operations of structures, systems, or components that could affect nuclear safety; and i.
Reports and meetino minutes of the RDC.
AUDITS 6.5.2.8 Audits of station activities shall be performed under the 1
cognizance of the NRB.
These audits shall encompass a.
The conformance of station operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months; SHOREHAM - UNIT 1 6-7 e,
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I M INISTRATIVE CONTROLS t
3 3 2), (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 occurrine in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per year; 6.
ins st rfernst:e of m=tivities required by the Quality Assurance Trcera. to eeet the criteria of Appendix 3, 10 CPR Part 50, at least once per 24 monthat e.
The fire protection programmatic aontrols including the implementing procedures, equipment and program implementation at least once per 24 months utilising either a cualified offsite licensee fire protection engineer (s) or an outside independent fire protection consultant.
I f.
Any other area of station operation considered appropriate by' the i
NRP,- President or the Assistant Vice President - Nuclear operations c.
The radioloeical environmental monitorino prooram and the results i
thereof aL least once per 12 months; h.
The OTTSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; and 1.
The PROCESS CONTROL PROGRAM and implementinc procedures for
,solidificatiens of radioactive wastes at least once per 24 months.
The performance of activities required by the Quality Assurance Procram for effluent and environmental monitoring at least once per 12 months.
RECORDF 6.5.2.9 Records of NRS activities shall be prepared, approved, and l
distributed as indicated below:
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 meeting.
b.
Reports of reviews encompassed by Specification 6.5.2.7 shall be prepared, approved, and forwarded to the President and the Assistant Vice President - Nuclear Operations within 14 days i'
following completion of the review.
SHOPEHAM - UNIT 1 6-8
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ADMINISTRATIVE CONTROLS M (Continued) c.
Audit reports encompassed by specification 6.5.2.0 shall be forwarded to the President, Assistant Vice President - Nuclear operations and to the management positions responsible for the aress audited within 30 days after completion of the audit by the auditing organisation.
i 12 6 REPOPTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTA3LE EVENTS:
a.
The commission shall be notified and a report submitted pursuant 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.
t 6.7 PROCEDURES AND PROGRAMS 6.7.1 Written procedures shall be established, implemented, and maintained covering the activities referenced belew:
a.
The applicable procedures recommended in Appendix A of Requ1 story Guide 1.33, Revision 2, February 1978.
b.
The applicable proceoures required to implement the requirements of NUPIG-0737.
c.
Tuel handling operations.
d.
Surveillance and test activities of safety-related equipment.
s e.
Security Plan implamentation.
f.
Emergency Plan implementation.
q.
Fire Protection Procram implementation.
h.
PROCESS CONTROL PROGRAM implementation.
J.
OFTSITE DOSE CALCULAT20N MANUAL l'p1Ementation.
a j.
Quality Assurance Program for affluent and environmental monitoring.
5 SHOREMAM - UNIT 1 6-9
i c
g k2sTRATIVE CottTROLS 6.7.2 Each procedure of specification 6.7.1, and changes thereto, shall be reviewed by the ROC prior to implementation.
The Plant Manacer shall approve station Administrative procedures, Security Plan implamenting 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 Manaaer prior to implementation.
Each Plant Division Manager shall be responsible for a t
desionated set of procedures.
These procedures shall be reviewed l
periodically as set forth in administrative procedures.
6.7.3 Temporary changes to procedures of specification 6.7.1 may be made provided:
a The intent of the original procedure is not altered b.
The chance is approved by two members of the unit management t:: on shiftp ataff, at least one of whom is qualified as ::
^ {.g.md:r:,' :6 g r
and c.
The chance is documented, reviewed by the ROC, and approved by the Plant Manager within 14 days of implementation.
6.7.4 The ic11owina programs shall be established, implemented, and maintained:
a.
Padicactive Effluent Controls Procram 5
A procram shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining doses to MEMBERS OF THE PUBLIC from radioactive affluents as low as reasonably achievable.
The program (1) shall be contained Jn the CDCM, (2) shall be implemented by operatina procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The procram shall include the following i'
elements:
1)
Limitations on the operability of radioactive liquid and l
gaseous monitorino instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the CDCM.
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SHORERAM - Uti2T 1 6-10
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Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix 3, Table !!, Column 3,
3)
Nonitoring, sampling, and analysis of radioactive 11guld and gaseous 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 commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix 2 to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions u
from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodoloay and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous eff.1. dent treatment systems to ensure that the appropriate portions of these systems are used to reduce releasee of radioactivity when the projected doses in a 31-da*; period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix 2 to 10 CFR Part 50, 7)
Limitations on the dose rate resultino from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conformina to the doses associated with 10 CFR Part 20, Appendix 3, Table 22, Column 1, 8)
Limitations on the annual and quarterly air doses taeulting from noble eases released in gaseous effluents 920m each
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unit to areas beyond the SITE BOUNDARY conferr4;,q to Appendix 2 to 10 CFR Part 50, j
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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 gaseous effluents released from each unit to areas beyond the SITE SOUN,DARY 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.
Radioloolcal Environmental Monitorine.Pronrap
A prooram shall be provided to monitor the rad.ation and radionuclides in the environs of the plant.
The program shall provide (1) representative measurements of radioactivity in the hiehest potential exposure pathways, and (2) verification of.the accuracy of the affluent monitoring program and modeling of l
environmental exposure pathways.
The program shall (1) be L
contained ~in the CDCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and. (3) include the following 1)
Monitoring, sampling, analysis, and reportino of radiation I
and radionuclides in the environmor.t in accordance with the l
methodology and parameters in the CDCM.
2)
A Land Use Census to ensure that chances in the use of arena
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at and beyond the SITE SOUNDARY are identified and that i
modifications to the monitoring program are made af required by the results of this census, and 3)
Participation in a Interlsboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measureme' ts of radioactive materials in n
environmental sample matrices are performed as part of the quality assurance program for environmental monitorina.
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ADMINISTRATIVE CONTROLS 5.8 REPORTING REQUIREMENTS ROUTIKE RIPOPts 6.8.1.In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to i
the. Regional Administrator of the Regional office of the NRC unless otherwise noted.
I ANNUAL REPORTF 6.8.1.1 Annual reports covering the activities of the unit as described i
below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report was submitted prior to March 1 of the year that followed initial criticality.
5.8.1.2 Reports required on an annual basis shall include a tabulation on an annual basis of the number of station, utility, and other personnel (includino contractors) receiving exposures greater than 100 mrems/yr and their associated manrem exposure according to work and job functions *
(e.g., operations and surveillance, inspection, routine maintenance, special maintenance (describe maintenance), waste processino, and fuel handlino).
The dose assianments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeters (TLD), or film bados measurements.
Small exposures totallino less than 20% of the individual total dose need not be accounted for.
In the accrogate, at least 80% of the total wholebody dose received from external sources should be assioned to specific major work functions.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.8.1.3 The Annual Radiolecical Environmental operating Report covering the operation of the unit durino the previous calendar year shall be submitted before May 1 of each year.
The report shall include summaries, interpretations, and analysis of trends of the results of the Radioloaical Environmental Henitoring Procram for the reportino period.
The material provided shall be consistent with the objectives outlined in (1) the CDCM and (2) Sections IV.S.2, IV.S.3, and IV.C of Appendix 2 to 10 CFR Part 50.
'This tabulation supplements the requirements of 20.407 of CFR Part 20.
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g SEMIANNUAL RADICACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 The semiannual Radioactive Effluent Release Report covering the operation of the unit during the previous 6 months of operation shall be submitted within 60 days after January 1 and July 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous ef fluents and' solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the CDcM and PCP and (2) in conformance with 10 CFR 50.36a and section IV.S.1 of Appendix ! to 10 CFR Part 50.
PPECIAL REPORTA 6.8.2 special reports shall be submitted to the Recional Administrator of the Regional office of the NRC within the time period speelfied for each report.
6.9 RECORD RETENTION 6.9.1 In addition to the applicable record retention requirements of Title 10, code of Federal Reculations, the following records shall be retained for at least the minimum period indicated.
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6.9.2 The following records shall be retained for at least 5 years:
a.
Records and loss of fuel handling operations.
b.
Recerds and loss of principal maintenance activities, j
inspections, repair, and replacement of principal items of equipeent related to nuclear safety.
I c.
All REPORTABLE EVENTS.
l 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.
g.
Records of sealed source and fission detector leak tests and results.
l SHCRENAM - UNIT 1 6-14
ADMINISTRATIVE CONTROLS
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b.
Records of annual physical inventory of all sealed source material of l
record.
6.9.3 The following' recordt shall be retained for the duration of the unit Operating Licenses e.
Records and drawine changes reflecting station design
)
modifications made to systems and equipment described in the Final Safety Analysis Report.
I b.
Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
c.
Records of radiation exposure for all individuals issued
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monitorina devices in accordance with 10CFR20.202.
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d.
Records af gaseous and liquid radioactive material released to the environs.
e.
Records cf training and qualification for curr~nt members of the e
unit staff.
f.
Records of quality assurance activities required by the Quality if Assurance Manual which are not listed in Section 6.9.2.
e.
Records ef reviews performed for chanoes made to procedures or equiprent or reviews of tests and experiments pursuant to 10 CFR l
50.59.
h.
Records of meetinos of the ROC.
1.
Records of analyses required by the radiological environmtntal monitorina program that would permit evaluation of the accuracy 1
of the analysis at a later date.
This should include procedures f
effective at specified times and QA records showins that these l
procedures were followed.
I
.j.
Records of reviews performed for chanees made to the OFFSITE DOSE CALCULATION MANUAL and the PROCESS CONTROL PROGRAN.
6.10 RADIATION PROTECTION PROGRAM I
Procedures for personnel radiation protection shall be prepared 6.10
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consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
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ADMINTSTRAT2VE CONTROLS 6.11 NIGH RADIATION AREA 6.11.1 In the it$e of the ' control device' or ' alarm signal' required by paragraph 20,202blj+)) of 10 CPR Part 20, each high radiation area in whnch the intensity of radiation is greater than 100 mroms/h but less than 1000 mress/h shall be barricaded and conspicuously pated as a high radiation area and entrance thereto shall be controlled by requiring issuance of a L
Radiation 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 following:
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 aress with this.
monitoring device may be made after the dose rate levels in the i
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 monitorino device, who is responsible for providino positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the j
Health Physics Enoineer in the RWP.
l 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 the body could receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose creater than 2000 exams shall be L
provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Watch Supervisor on duty and/or the Health Physics Engineer.
Doors shall remain locked except during priods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in that area.
For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months a dose in excess of 2000 arems** 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 durine the performance of their assioned radiation protection duties, provided they are otherwise followine plant radiation protection procedures for entry into hich radiation areas.
Neasurement made at 18 inches from source of radioactivity.
SHOREHAM - UNIT 1 6-16 l
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o-I ADEIFISTRATIVE CONTROLD where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be
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l roped off, conspicuously posted, and a flashing light shall be activated as j
a warning device.
In lieu of the stay time specification.of the RWP, continuous surveillance, direct or remote.(such as use of closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures,to provide, exposure control over the activities within the area.
6.12 PPoetss CONTROL PROGRAM (PCP) changes to the PCP s.
Shall be documented and records of reviews performed shall be re tained as
required by speelfication 6.9.33 This documentation shall centains 1) suffielent information to support the change toesther with I
the appropriate analyses or evaluations justifying the chance (s) and 2)
A determination that the change will maintain the overall conformance of the solidified waste product to existino requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the ROC and the approval of the Plant Manager.
i 6.13 OTTF77E DOSE CALCULATION MANUAL (ODCM)
Changes to the CDCM:
a.
Shall be documented and records of reviews performed shall be retained as required by specification 6.9.3j.
This documentation shall contains 3) sufficient information to support the chance together with the appropriate analyses or evaluations justifying the change (s) and
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EHORENAM - UNIT 1 6-17
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A determination that the change will maintain the level of l
radioactive effluent control regired by 10 CFR 20.106, 40 j
CFR Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part l
50 and not adversely impact the accuracy or reliability of effluent, dose, er eetpoint calculations.
l b.
Shall become effective after review and acceptance by ROC and the y
approval of the Plant, Manager.
i c.
Shall be submitted to the Commission,in the form of a complete, 1egible copy of the entire ODCN as a part of or concurrent with the semiannual Radioactive Effluent Release Report for the period of the report in which any change to the CDCN 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 l
change was ik.plemented.
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v t e Letter Sequence Meeting
TAC:75846, (Open)
Initiation Request Acceptance... Administration Meeting Questions Answers Results Approval... Other: ML20059A635
MONTHYEAR1990-06-27 [Table View]

ML20055D291

Text

Dear Mr. Steiger:

SUBJECT:

Enclosure:

Dear Mr. Steiger:

SUBJECT:

Enclosure:

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