ML20070H619
| ML20070H619 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 03/11/1991 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20070H617 | List: |
| References | |
| NUDOCS 9103140323 | |
| Download: ML20070H619 (20) | |
Text
_ . _ _ _ . _ _ _ _ . . _ _ _ . _ _ . _ _ _ _ _ . . . . . ._ _ . . _ . _ . _ . _ _ . . . _ . . _ . _
. . LEEEE t1MITING _CONDITIONS _ _ _ _ _ _ _ _ _ _ _ _ _FOR
_ _ _ _ FUEL
. _ _ _ _ _HANDL'_ING _OPERATION & SURVEILLANCE i _ _______ _ _ _ _ _ _ _ - - _ _ _ - -_
, S'ECT10N pJor ust D) PAGE 2.0 SAFETY LIMITS AND LIMITING SAFETi SYSTEM SETTINGS)... 2II 3/4.0 APPL 1CA!!LITY.................................... 3/4 0 1 3/4.1 INSTRUMENTATION 3/4.1.1 MONITORING INSTRUMENTATION >
i Radiation Monitoring Instrumt.ntation............ 3/4 1-1 l
Sei smic Moni toring Ins trumenta tion. . . . . . . . . . . . . . 3/4 'l-4 Meteorological Nanitoring Instrumentation....... 3/4 1-7 l 3/4.2 CONTAINMENT SYSTEMS (NOT USED)................... 3/4 2-1
! 3/4.3 ILANT_lYlTEMI i
3/4.3.1 S E AL ED S OURC E CONT AMI N AT I ON. . . . . . . . . . . . . . . . . . . . . . 3/4 3-1
, 3/4.3.2 SITTLEMENT OF REACTOR BUILDING ,
Total Settlement.................................. 3/4 3-3 l Differential Settlement Across The Structure..... 3/4 3 4 Penetration Differential Settlement.............. 3/4 3 5 ,
h 3/4.3.3 AREA TEMPERATURE MONITORING....................... 3/4 3-7 i
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l DESIGN FEATURES i
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SECTION --
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501 $1TE !
I Exclusion Area........................................ 5-1 !
Low Population Zone......... ......................... 5 ' i
-i F
SITE BOUNDARY for Radioactive Gaseous and Liquid '
Effluents........................................... 5-1 ;
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_5._2__C_O_N.T..A.I._N_M_E_N_T ;
Configuration......................................... 5-1 l f
Disign Temperature and Pressure....................... 5-1 l 6
Secondary _ Containment................................. 5-2 i t !
Lf_QEEEpiE) ML ^* CouTfdt* Goo DA rA l FuelAssemblies.......................................5k f Control Rod Assemblies................................ 5 b !
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[5_. _4_ _R _E _A.C .T _O _R _ _C .O O_L__ _A_N _T _ _S _Y _S _T _EN Design Pressure and emperature....................... 5-6 :
Q 1ume................................................ 5- j 3
5 . 3 M E T E O R O L O G I C A L T O W E R L O C A T 10 N . . . . . . . . . . . . . . . . . . . . . . . . . . 5 -86 f 4- 1
_5 . g__F_U_E _L __S _T_O_R _A_G _E - :
i Criticality...........................................5/6 l Drainage..............................................5d6 f r
Capacity.............................................. 5 66 -;
5.1 COMPONENT CYCLIC OR TRANSIENT LIMIT.................... 5-7 j t
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- c DEFIN1TIONS FREQUINCJ_ NOTATIONS 3.6 The FREQUENCY NOTATION specified for the performance of Surveillance
- Requirements shall correspond to the intervals defined in Table 1.1.
FUEL HANDLING OPERATIONS 1.7 FUEL HANDLING OPERATIONS shall be the movement of fuel over or within
, the Spent Fuel Pool. Suspension of FUEL HANDLING OPlRATIONS shall not p r e c l u d e c o m p l e t i o n o f t h e m o v e m e n t o f f u e lf-e qu i pe W ef'-somp efrep4-ys to a safe conservative position.
MEM!ERi OF THE PUBLIC 1.8 MEMBER (S) 0F THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include. employees of the utility, its contractors or vendors.- Also excluded from this category are persons who enter the site to service 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. OFFjllf_ppj{_{fl{ykfIlpy_gfypfl_(ODCM) 2,9 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent maaitoring Alarm / Trip Setpoints, and in the conduct of the Radioluvical Environmental Monitoring Program. The ODCM shall also contain (3) the Radioactive Effluent Controit 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 'l 1 SHOREHAM UNIT 1 1-2 i
e . s SECTION 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS u s s.o (NOT Q l 2-1 1
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. 3/4.4. ELECTRICAL POWER SYSTEMS ;
344.4.1 A.C. SOURCES LIMITING CONDITION FOR_ FUEL _ HANDLING _ OPERATION 3.4.1.1 One circuit between the offsite transmission network and the onsite distribution system and one diesel generator shall be OPERABLE. APPLICABILITY: "c. FUELED MODE * # ACTION: With one of the above A.C. sources not OPERABLE suspend handling of irradiated fuel in the secondary containment and crane operations over the spent fuel storage pool when fuel assemblies are stored therein. 3 SURVEILLANCE REpVIREMENTS, 4.4.1.1 The above required independent circuit'between the offsite transmission network and the onsite AC distribution. system shall be determined OPERABLE at least once per 7 days by verifying correct-breaker alignments and indicated power availability. 4.4.1.2 The above required diesel generator shall be determined OPERABLE at least once per 7 days by verifying _ correct breaker - alignments and indicated power ~ availability. 4.4.1.3 The above required diesel generator shall be demonstrated OPERABLE: i a. At least once per 92 days by:-
- 1. - Verifying that the day fuel tank contains a_ minimum of 275-gallons of fuel.
- 2. Verifying the fuel storage tank contains-a minimum of 20,412-gallons.
T-~Thi specTTTi3 diesel generator shall, be OPERABLE only when l handling- fuel in the secondary containment. l f OPERABILITY of A.C. sources is_ unaffected'by the use-'of--commercial' , '- O f ;;;t r, p;r grade _ (non-Category I) parts.3.maOrte:S thet t. th: ;;: : . _ gar n a n ,,vI. v t- . gs . c r, r. r. m.. .
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324.4.2 , ONSITE POWER DISTRIBUTION SYSTIMS , , LIMITING CONDITION FOR FUEL HANDLING OPERAT!0N _ 3.4.2.1 As a minimum, two of the following A.C. system divisions, and one D.C. power distribution system division which corresponds to @J' OPERABLE diesel generator shall be OPERABLE and energized: an
- a. A.C. power distribution: [
- 1. Division 1 consisting of:
) a) 4160 volt A.C. bus 101.
; b) 480 volt A.C. bus ill and MCCs 1110 through 1116, 1118, 1119, Illy and 1112.
c) 120-volt A.C. distribution panels R1, R2, and R3.
- 2. Division 2 consisting of' IL a) 4160 volt A.C. bus 102 b) 480 volt A.C. bus 112 and MCCs 1220 through 1126, 1128, 112g, and 112X.
c) 120-volt A.C. distribution panels in B1, B2 and B3.
- 3. Division 3 consisting of:
a) 4160 volt-A.C. bus 103 t) 400 volt A.C. bus 113 end MCCs 1133 and 1134, c) 120 volt A.C. distribution panels 01 and 02.
- b. D.C. power distribution:
- 1. Division I consisting of 125 volt D.C. distribution bus A.
- 2. Division 2 consisting of 125-volt D.C. distribution bus B.
[
- 3. Division 3 consisting of 125-volt D.C. distribution bus C.
APPLICABILITY: DEPUELED MODE * # 7'~Thi DTI!~pc e~ distribution system shall be OPERABLE only when handling fuel in the secondary containment. l f OPERABILITY of Onsite Power Distribution Systems is unaffected _by 1 ' theuseofcomm_treialgrade(no_nC_ategory__1)partsypr0 Vie:c=tti.-
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l pgECTRICAL POWER SYSTEMS LIMITING CONDITION FOR FUEL HANDLING OPERATION _ICONTINylDj_____ ACTION:
- a. With one division of the above required two A.C. divisions not energized, suspend handling of irradiated fuel in the secondary containment and immediately initiate action to restore the required A.C. divisions.
- b. With the D.C. division associated with OPERABLE diesel generator not energized, suspend handling of irradiated fuel in the secondary containment and crane operations over the spent fuel storage pool when fuel assemblies are stored therein.
ENEEElkkhb$$.BfQU1REMENT5 4.4.2.1 The above required power distribution system divisions shall be determined energized at least once per 7 days by verifying correct breeker alignmert and voltege on the tusses and power availability.to the MCCs and the panels. T l SHOREHAM - UNIT 1 3/4 4 4
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- 344.4 ELECTRICAL POWER SYSTEMS l 3
BASES t 3/4.4 21 AND 324.4.2 A.C. SOURCES AND 0NSITE POWER DISTRIBUTION SYSTEMS ! TheOPERABILITYofthespecifiedA.C.powersourchandassociated l distribution systems during fuel storage and handling ensures that i sufficient instrumentation and control capability is available for ! m9nitoring and maintaining the unit status. The use of commercial I grade parts is acceptable because these systems are not performing l safety related functions. l i i i l l i l I i
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, , l 4 '5.0 DESIGN FEATURES
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5.1 $1TE EXCLUSION AREt . 5.1.1 The exclusion area shall be as shown in Figure 5.1.1-1. L'0W POPUL ATION 20NE 5.1.2 The low population zone shall be as shown in Figure 5.1.2-1 i $1TE BOUNCARY FOR RADIDACTIVE GASEOUS AND L10VID EFFLUENTS 5.1.3 The SITE BOUNDARY for radioactive gaseous and liquid effluents shall I be as shown in Figure 5.1.3-1 5.2 CONTAINMENT CONFIGURATION _ 5.2.1 The primary containment is e steel lined reinforced concrete structure consuting of a drywell and suppression pool. The drywell is a
) steel-lined reinterced concrete vessel in the shape of a truncated cone !
closed by a hemispherical dome and is attach 2d to the cylindrical ! The drywell floor separates the drywell from the
/suppressionpool.
suppression chamber. The drywell design is for a minimum free air volume of 192.500 cubic feet. The suppression pool design is for an air region of I 134.000 cubic feet and a minimum water region of 76,870 cubic feet.
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i f DESIGN TEMDERATURE AND PRESSURE 5.2.2 The primary containment is designed for:
- a. Maximum internal pressure: 48 psig.
( b. . Maximum internal temperature: dryWell 340'F. suppression pool 225'F
- c. Maximum external pressure: 4.7 psid,
- d. Maximum floor differential pressure: 30 psid, downward 5.5 psid, upward SHOREHAM UNIT 51 e
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H DEEtGN FEATURES , l SECONDARY CONTAINMENT 1 i 1 5.2.3 The secondary containment consists of the Reactor Building, the equipment access structure and a portion of the main steam tunnel and has a design minimum free volume of 2,000,00C cubic feet.
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SITE BOUNDARY FOR RADICACTIVE ' GASEOUS AND LIQUID EFFLUENTS FIGURE 5.1.3-1 SHOREHAM - UNIT 1 b5-4
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bESIGN FEATURES
$h72OIbCC@ FUEL A~D rpacu. ROO DATA
, FUEL ASSEMBt1ES
- sg4 ke t $brane > t 5 d.'1 The OmeTTwe 4t ftEipA4 contains560 fuel assernblits with each fuel assembly containicg 62 fuel rods and two water rods clad with Zircaloy-2.
of 150 inches.Et The ch fuel rod gere Qn.,fligi is destp"'Ane3i3ekitned_M.h_37a m- maxima,d to have a no everage enrichment of 1.f0 weight percent U 435. %% CONTROL ROD ASSEMBLIES ~ 2, %. are. 5.7.'2 Ght_tetrapr core as o+Fienee ai_n)137 to con _t_/ control rod assemblies, each consisting of a cruciform array of stainIess steel tubes containing 143 inches of boron carbide, B 0, 4 powder surrounded by a cruciform shaped stainless steel shnath.
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S.4 REACTOR COOLANT SYSTEM PES!GNFF.ESSUREANDTEMPERATURE ( 5.A.1 The reactor coolant system is designed:
- a. For a pressure of:
- 2. 1150 psig on the suction side of the recirculation pump,
- 2. 1325 psig from the recirculation pump discharge to the outlet side of the discharge shutoff vo'Ive.
3, 1325 psig from the discharge shutoff valve to the jet pumps, l
- b. For a temperature of'562'F.
VOLUME 5.4.2 The total water and steam volume of the reactor vessel and recirculation system is designed to be approximately 16.410 cubic feet at a e s~ -- l nominal T,y, ~of 533 { SHOREHAM - UNIT I 5-5 l e
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DESIGN FEATURES ( l
. 3 5.Tf METEOROLOGICAL TOWER LOCATION 3
5.5?1 The 400 foot meteorological tower is located as shown on Figure 5.1.3-1. l 4 1
- 5. F FUEL STORAGE CRITICALITY u
5.@f1 The spent fuel storage reeks are designed and shall be maintained with: i
- a. A L,ff equivalent to less than or equal to 0.95 when flooded with unborated water, which includes a conservative allowance of 1.0%
delta L/k for uncertainties as described in Appendix 9A of the SAR.
- b. A nominal 6 inches in one direction and 9.25 inches in the other direction center-to center distance between fuel essemblies placed in the storage racks.
- 5. 6.1. 2 The k,ff for new fJe1 for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous moderatir,n i 4.ssured g - -
DRAINAGE 4, 5$.'2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 152'- 4 1/2". CAPACITY 4, 5 $'3 The spent fuel storage pool is designed and shall be mainthined with e storage capacity limited to no more than 2176 fuel assemblies, e m-. - 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT { _ 5.7.1 The components identified in Table 5.7.1-1 are designed and shall b Qntained within the cyclic or transient limits of Table 5.7.1-1. SHOREHAM - LINIT 1 S-6
TABLE 5.7.1-1 -
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COMPONENT CYCLIC OR TRANSIENT LIMITS
'N Cyclic OR DESIGN CYCLE 3 COMPONENT TRANSIENT LIMIT OR TRANS!ENT \ ,
Reactor 120 heatup and cooldown cycles 70'F to 560'F to 70'T 80 step change cycles Loss of all-feedwater heaters 180 reactor trip cycles 100% to 0% of RATED THERMAL-POWER ( 130 hydrostatic pressure and Pressurized to >~ 930 and leak tests '- g 1250 psig
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Sh0REHAM - UNIT 1 5-8 w_ _ 7 .
6 ;p 0 & ADMINISTRATIVE CONTROLE - 6.1 RESPONSIBILITY 6.1.1 The Plant Manager shall be responsible for the managerient of the overall plant and ensuring the safe storage and handling of irradiat d fuel. The Plant Manager shall delegate in writing the succession to this responsibility during his absence.
%,es e mbr, 6.1.2
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atch i-gineer (or during his absence from the Control Room a de s i g na t e d[T A fuhetion, A my...de?Ji management shall be responsible directive to this for the Control effect, signedRoom by thecommand Vice President, Office of Nuclear shall be reissued to all station r -sonnel on an annual basis. . 622 ORGAN 123 10N 6.2.1 Nuclear Organization An organi?r+fon shall be established for the unit in the DEFVF'.ED MODE and for corporate management. This organization shall include the positions for activities af fecting the safe storage and handling of irradiated nuclear fue:
- a. Lines of authority, responsibility and comTonication shall be established and defined frum the highest :. magement levels through intermediate levels to and includitg all organization positions involved with the safe storage and handling of irradiated fuel. These relationships shall be docu ented and updated, as appropriate, in the form of organizational charts, fuictional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the SAR and updated in accordance with 10
. CFR 50.71(e),
- b. The respensible Vice President-shall have corporate res7ensibility for overall plant nuclear safety and shall take any mecsures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support t0 the plant to ensure the safe storage an+ handling of irradf ated fuel,
- c. The Plant Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities-necessary for safe maintenence of the plant and storage and handling of irradiated fuel.
- d. The individuals ~ho train the operating staff &nd those who carry out health physics and quality assurance functions t:, report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their' independence from operating pressures.
SHOREHAM - IINIT 1 6-1 I ' . c ,, * . [
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' ADMINISTRATIVE CONTROLS
, AUDITS (Continued) }
- b. The performance, training and qualifications of the entire staff at least once per 12 months;
- c. The results of actionb taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, et least once per year;
- d. The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix B, 10 CFR Part 50, at least once per 24 months;
- e. The fire protection progrur,matic controls including the implementing procedures, equipment and program imple'entation at least once per 24 months utilizing either a qualif'-
offsite ! licensee fire protection engineer (s) or an outside iidependent fire protection consultant.
- f. Any other area of station operation considered appropriate by the NRB, President or the Vice President, Office of Nuclear; R E M P
- g. The f%diological @$vironmental $onitoring @fregram and the results ,
thereof at least once per 12 months;
- h. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at lea't once oer 24 months; and
- i. The PROCESS CONTf.0L PROGRAM and implementing procedures for solidificationCTof radioactive-wastes at letst once per 24 months.
- j. TFe performance of activities required by the Quality Assurance regram for effluent and environmental monitoring at least once ,
per 12 months. RECORDS 6.5.2.9 Records of NRB activities shall be prepared, approved, and distributed as indicated below:
- a. Minutes of each NRB meetd shall be prepared, approved, and forwarded to the Presidet.. .nd the Vice President. Office of e Nuclear 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 ' vice President, Office of Nuclear within 14 days following completion of the review. SHOREHAM - UNIT 1 6-8
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ADMINISTRATIVE CONTPOLS 7 ___ __ 7 ._. 6.7.2 Each proce Tre of Specification 6.7.1, and changes thereto, shall be reviewed by the C prior to implementation. The Plant Manager shall approve Station Administrative proctdures, Security Plan implementing procedures and mergency Plan implementing Procedures prior to implenentation. Other proceduces of Specification 6.7.1-shall be approved by the appropriate plant Divi 4on Manager or by the Plant Manager prior to implementation. Each Plant Division Manager shall be responsible for a cesignattd set of procedu"os. These procedures shall be reviewed periodically as set forth in administrative procedures. 6.7.3 Temporary ch,anges to procedures of Specification 6.7.1 may be made provided:
- a. The intent of the original procedure is not altered;
- b. The change is approved by two members of_the unit man 3gement sta f f, et least one of whom holds a Senior Reactor-Operators License on the unit affected; and
- c. The change is documented, reviewed-by-the ROC, and-approved by i the Flar.t Manager within 14 days of implementation.
- 6.7.4 . The folicv
- ing programs shall be established,. implemented, and maintained:
l
- a. 11ffolgtfyg_Efflugn1_ Cop 1Ipis_fIggram L A program shall be provided c. forming with-10 CFR 50.36a for the l control of radioactive effluen and for maintaining doses to l MEMBERS OF THE PUBLIC from rad ctive effluents as low as reasonably achievable. The program (3) shall be contained in the ODCM, (2) shall be implemented by operating procedures,.and (3) shall include remedial actions to be taken whenever the program i limits are exceeded. The program shall include the following i elements:
- 1) Limitations on the operability of-radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the o
methodology in the ODCM. l SHOEEHAM - UNIT 1 6-10
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- ADMINISTRATIVE CONTROLS
- h. Records of annual physical inventory of all sealed source material of record.
6.9.3 The foilowing records shall be t>tained for the duration of the unit Operating License:
- a. Records and drawing changes reflecting station design modifications made to systems and equipment described in the Final Safety Anr. lysis Report,
- b. Records of new and irradiated fuel inventory, fuel transfers, and assembly burnup histories.
- c. Records of radiation exposure for all individuals issued monitoring devices in accordance with 10CFR20.202,
- d. Recorda of gaseous and liquid radioactive material released to the environs,
- e. Records of training and quclification for current members of the unit staff,
- f. Records of quality issurance activities required by the Quality Assurance Manual which are not listed in Section 6.9.2.
- g. Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
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- h. Records of meetings of the ROC and NRB.
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- 1. Records of analyses required by the 3ddiological @hvironmental M eonitoringFptogram that would permit evaluation of the accuracy
. of the analysis at a later date. This should include procedures effective at specified times and QA records showing that these procedures were followed.
J. Records of reviews performed for c$tfiget made to the OFFSITE DOSE ' CALCULATION MANUAL and the PROCESS (ddis0L PROGRAM. 6.10 RADIATION PROTECTION PROGRAM 6.10 Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure. SHOREHAM - UNIT 1 6-15 _ _.}}