ML20236F674
| ML20236F674 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 10/19/1987 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20236F650 | List: |
| References | |
| NUDOCS 8711020259 | |
| Download: ML20236F674 (12) | |
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- NUCLEAR REGULATORY. COMMISSION ,: -
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-? (...;. 4 LONG ISLAND' LIGHTING' COMPANY' j
4 DOCKET NO. 50-3223. . ,
SHOREHAM NUCLEAR POWER STATION ,
AMENDMENT-TD FACILITY OPERATING LICENSE' l AmindmentlNd.: 81. . M
- LicenseNopNPF-36l j
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- 1. The Nuclear Regulatory Comission (the Comission) has;found(tha'tj ' '
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. . . . . , , . , d A. The! application for amendment by Long; Island: Lighting Company a L
(thelicensee),'datedJanuary:12,.1987,' complies with the . ~ A
. standards and requirements of theJ Atomic Energy Act of 1954, as::
- amended (the Act), and> the Comission's rules .and?regulationsiset.
forth in.10 CFR Chapter I;1 _
B. . .The facility will. operate ,in cohfomity With)the1 application,ithel provisions.of the Act, and the rules and:regulationstof the '
1 Comission; 1
C. There is reasonable.assur'ance (i)"that thelactivitiestauthorized by; this amendment can be conducted.without endangering the health and E . '
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safety of the public,'and-(ii.) that such' activities:will:be" conducted '
in; compliance.with-the Comission's regulations; > '
D. The issuance.of this amendment will not be inimical'to the common) . '
s defense and security or to the.healthiand: safety of the;public;: and- .
- q E. 'Theissuance'ofthisamendmentisinaccordancewith!10'CFRPart51 1 of the Comission's regulationscand all applicable.requirementsLhave ~ R been' satisfied.
- 2. Accordingly, the license'is amended by changes to theITechnical Specifications l as indicated in the attachment to this license. amendment, sand; paragraph 2.C.~(2); !
of Facility Operating License No.1NPF-36._is;hereby amended to read as;follows: j Technical' Specifications j The TechnicalJSpecifications contained in;Ap'pendix'A'and the' l Environmental: Protection. Plan contained fin: Appendix l B,Las revised N through Amendment No. .8 are.hereby incorporated into5thislicense.
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U Long; Island Lighting Company shall? operate:the;facilityLint . .. , n accordance with the Technical Specifications:andithe Environmental; Protection-Plan.- .
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- p ,f3.V OTh~isilidense amendment is' effective 'astof11ts datetofdssuance.z '
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- FOR ;THE NUCL EAR . REGUL ATORYJ COMMISSION !
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,Walte'ri R. T Butleri; Director (,
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Attachment:
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< l Changes:to theLTechnical < r i .
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iSpecificationst 67 "
Y"' p L Date ofrIssuance:1 October!19, 1987 '
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- 3. This . license amendment is effective as of its date of issuance. .
FOR THE. NUCLEAR PEGULATORY COMMISSION' L Walter R. Butler, Director.c Project Directorate I-2 Division of. Reactor, Projects 1/II
Attachment:
Changes to the Technical Specifications . Date of Issuance: October 19, 1987
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k ATTACHMENT TO LICENSE. AMENDMENT NO. 8 FACILITY OPERATING LICENSE.NO. NPF-36 [ DOCKET NO. 50-322 1 Replace the following pages of the Appendix "A"1TechnicalJSpec'ifications with' the' attached pages. The revised pages are identified by Amendment number ands - contain vertical. lines. indicating.the area of change. Overleaf pages provided "
' to maintain docurrent completeness.*' 'i Remove Insert-1 5-3 5-3L 5-4* 5-4* il l- 5-5 5-5' 5-6* '5-6*
5-7 5-7 t 5-8* 5-8* 6-5* 6-5* 6-6 6-6 l l 1 1 i
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SHORENAM - UNIT 1 5-3 Amendment No. 8- =__-_-________
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T$'deohn, y 6,: dM i SITE BOUNDARY FOR RADIOACTIVE GASEQUS AND LIQUID EFFLUENTS FIGURE 5.1.3-1 SMORENAM'- UNIT'1 5-5 meerdment 2. ' 8L 1
DESIGN FEATURES , 1
- 5. 3 REACTOR CORE FUEL ASSEMBLIES e #w@+ ~/4 %.co' 5.3.1 The reactor core shall contain 560 fuel assem&ttes.3withieadhtfuel' I assembly containing 62 fuel rods and two water rods clad with Zircaloy-2.
Each fuel rod shall have a nominal active fuel. length of 150-inches. The: . -{
.percent initial core U-235.
loading shall-have a maximum average enrichment of 1.90l weight core loading, Reload fuel.shall be similar.in physical design;to the initial 1 j 4 1 CONTROL ROD ASSEMBLIES i 5.3.2_ The reactor core shall contain 137 control rod assemblies, each- l j consisting of a cruciform array of-stainless steel tubes containing=143 inches j of boron carbide, 8 4C, powder surrounded.by a cruciform shaped stainless steel sheath. ' J 5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE l 5.4.1 The reactor coolant system is designed and shall be maintained: a. In accordance with the code requirements specified in Section (5.2)' I of the FSAR, with allowance for normal degradation pursuant to the i applicable surveillance requirements, i
- b. For a pressure of: '
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- 2. 1150 psig on the suction side-of the recirculation pump, 1325 psig from the recirculation pump discharge to the' outlet side of the discharge shutoff valve. '
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- 3. l 1325 psig from the discharge shutoff valve to the jet pumps,
- c. For a temperature of 562*F.
VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is.approximately 16.410 cubic feet at a nominal T;y, of 533*F. gp gWh I L
.SHOREHAM - UNIT 1 5-6
_ _ _ . _ _ _ _ _ .__[._____.__________._______________________________._ _ _'s__ __ _ _ _ . _ ____m____ .__
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4 1, < . k u_ _ ___ ,.s . DESIGN' FEATURES 5.5 METEOROLOGICAL TOWER LOCATION ~ > f
- 5.5.1 The 33 foot. meteorological tower shall;be located as shown on _
Figure 5.1.1-1. -The 400Lfoot. meteorological tower shall,beflocated as shown' on Figure 5.1.3-1 . , 5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks-are: designed and sha11Lbe maintained with:
- a. A k,ff equivalent to less than or'equalito 0.95 when; flooded with-unborated water, which indludes a ~ conservative allowance of:1.0%i delta k/k for' uncertainties'as described in Appendix 9A ofithe FSAR.
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- b. A nominal 6 inches inlone direction a'd n 9.25 inches.in the other.
direction center-to-center distance between fueliassemblies. U placed in the storage racks.
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5.6.1.2 The k,ff for new fuel for.the first core loading stored' dry in the spent fuel storage racks'shall'not exceed 0.98 when aqueous moderstion-is assumed. DRAINAGE 5.6.2 1he' spent fuel storage pool _isidesigned and shall be maintained.to prevent inadvertent draining of the pool below elevation 152'-4 ".
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CAPACITY ** 5.6.3 The spent fuel storage pool is designed and shall:be. maintained with a storage capacity limited to no more than 2176 fuel assemblies.- r 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT-5.7.1 The components identified in Table 5.7;1-11are designed and shall-bes maintained within.the cyclic or transient-limits of Table 5.7.1-1. L a. * *w ( ; 9
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;SHOREHAM - UNIT 1 5-7 Amendment' No.; 8 L m
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. TABLE 6J2.2 C l
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l MINIMUM SHIFTICREW COMPOSITION , E .i SINGLEruNIT" FACILITY: i' h.y NUMBER'0F T INDIVID'UALS REQUIRE S ~0 TO FILL POSITION! i
-POSITION- '
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> . CONDITION 1, 2, or'3 -
CONDITION 4 Lor 5' j ..; 1 4 o WE: L1- '
;SRO' :1:. -None:
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'l s, TABLE N'OTATI'ON, L
WE - Watch Engineer with-a Se'nior Reactorc0perators license lonLUnit 1.- SRO - Individual with a Senior Reactor Operatorsilicense on: Unit'1. u H RO - Individual with a Reactor-Operators license on Unit 1. Equipment' Operator a EO STA - Shift Technical Advisor
- M Except for.the Watch Engineer, the shift crew composition may befone less/than. H the mi'nimum' requirements of Table 6.2.2-1.for a. period'offtime;not)tofexceedl2 hours in order to accommodate unexpectedJabsence ofion-duty; shift: crew members" provided immediate action is.taken to. restore the.shiftJerew composition:.to ,3 within the' minimum requirements of Table:6'.2.2-1. . This' provision does not-permit any shif t crew position tolbe- unmanned: upon 'shif t chanoejdue' tojan) oncoming shift crewman beingl late or' absent. .,
Ouring'any absence..of'the Watch Engineer from1the control roo'm whileithe' unit- ' ~ is in OPERATIONAL CONDITION 1. 2'or 3,.an individual-(other.-than the Shifts .. a Technical Advisor) with a ' valid.: Senior Reactor: Operator license)shall bejdesig-" 3 nated to assume the control room command function; During any absence of<the. ' Watch Engineer from the control."roomLwhile the unit-is in' OPERATIONAL' CONDITION.'4" or' 5~, an individual with a valid:Seni.or' Reactori0peratorLlicense: or:. Reactorc Operator: license shall be designated /to" assume?the control ^ room command function, l-SHOREHAM - UNIT l' 1 6h5~ p ; .a 5 _.j l __._.____m_ m_ _ _ _ _ __ m.i .' 'l (
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? ADMINISTRATIVE CONTROLS
1612'.3" INDEPENDENT SAFETY ENGINEERING' GROUP (ISEG)- , ,
-FUNCTION
. 6.2.3;11The TSEG 'sh'all' function 1to' examine unit: operating. characteristics,-
NRCissuances",fi'n'dustryadvisories,ohicenseeEvent:Reposts,andother.'J sources?, of unit design and. operating; experience.information, includingiunits of'similar. design,-which may indicate areas for improving unitisafety. The ,ISEG;shall,
'make detailed recommendations for revised procedures -equipment;modificatic"ns,_
maintenance activities, operationt<acti,vities'or other means'o.f improvingzunit , safety,to the Director,(Quality Assurance, Safety and Compliance; '~ 1 1 COMPOSITION 6.2.3.2 -The ISEG shalli be composed of at le&st.five,'dedihated,l multi-; . _
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. discipl.ined, full-time engineers located: onl site. .; Each shall :have:a' bachelor's 1 degree in engineering or related science,1or: equivalent, land'at least'2 yearsi -
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; professional experience _in his field,;at,least 1,yearLof which experience;shall be in the~ nuclear field.
RESPONSIBILITIES 6.2.3.3 ~The ISEG shall'be responsible for. maintaining surveillance of unit ~ + activities to provide independent. verification
- that-these; activities-are'per-- ,
formed correctly and that human. errors 3 are reduced'as much as practical. N y RECORDS i i 6.2.3.4 Records of activities performed by the IS'EG shall:be prepared,' main-tained, and forwarded each calendar month to the; Director,-Quality Assurance, Safety and, Compliance. 6.2.4 SHIFT TECHNICAL ADVISOR ,
- 1 6.2.4.1 TherShift" Technical,Advisorshallprovideadvisoryitechhicalsupport !
to the WatchiEnginder.in the' areas:of thermal' hydraulics,: reactor engineering, l and plant analysis with regard to safe operation of the unit. The Shift
- l Technical Advisor.shall have a bachelor's' degree or_equivale'ntLin'.a scientific <
or engineering discipline and shall have' received specific. training'in theJ response and analysis of the unit for transients andiaccidents,;and in_ unit' o design and layout, including the capabilities of instrumentation'and: controls' in the control room.- ] 6.3' UNIT STAFF QUALIFICATIONS . 6.3.1 Each member of-the unit:stafffshal'1 meet ortexceed thelminimum qualifi .-
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cations of ANSI N18.1-1971 for comparable. positions and the: supplemental;. requirements'specified.in SectionsiA andiC;.of Enclosure 1Lof the March 28, 1980 NRC letter to all licensees..'except for:the Health Physics.: Engineer who shall: -[ meet or exceed the qualifications-of Regulatory L Guidefl.8,:Septemberfl975. The licensed Operators and Senior 10perators sha114alsoTeeeteor exceed the mini-- num' qualifications of the supplemental requirements specified in:. Sections A. and C'of Enclosure 1 of the March-28, 1980;NRC)1etter.to all licensees.,
*Not' responsible for sign-offLfunction.-
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