SNRC-2134, Proposed Amend 11 to License NPF-82,requesting Deletion of TS & Environ Protection Plan in Entirety
| ML20059H781 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 01/20/1994 |
| From: | Bortz A LONG ISLAND POWER AUTHORITY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-1357 LSNRC-2134, NUDOCS 9401310154 | |
| Download: ML20059H781 (100) | |
Text
{{#Wiki_filter:! Long Shoreham Nuclear Power Station Island P.O. Box 628 k-Power North Country Road Authority Wading River, N.Y.11792 i l I i 1 JAN2 01994 LSNRC-2134 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 Transmittal of Proposed Amendment 11 to LIPA's ; Possession Only License, No. NPF-82, and Appendices A and B, Technical Specifications and Environmental Protection Plan (Non-Radiological) Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 Ref: (1) LIPA Letter to USNRC, LSNRC-2115, dated November 4,1993; subject: License Change Application No. 2 Ladies and Gentlemen: i The Long Island Power Authority (LIPA) hereby submits, per a verbal request from the NRC staff, a typed version of proposed Amendment 11 to Possession Only License (POL) No. NPF-82 (Enclosure 1), 4 identical to Attachment 3 of reference 1. In addition, LIPA submits a marked-up copy of POL Appendices A and B (Technical Specifications and Environmental Protection Plan (Non-Radiological)) (Enclosure 2). As described in Attachment 1 of reference 1, LIPA is requesting deletion of the Technical Specifications and Environmental Protection Plan in their entirety. Should you require any additional information concerning this submittal, please do not hesitate to contact my office. Very ,uly yours, N O A. J Resi I}ortz t Manager Shoreham Station dyf/kc cc: L. Bell T.T. Martin C. L. Pittiglio R. Nimitz
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r e , E' a closure 1 ~ l i LONG ISLAND POWER AUTHORITY SHOREHAM NUCLEAR POWER STATION. UNIT 1 AMENDMENT TO POSSESSION ONLY LICENSE l DOCKET NO. 50-322 . Amendment No. 11 License No. NPF-82 i
- 1. The U.S. Nuclear Regulatory Commission (the Commission or the NRC) has found that:'
A. The application for this amended Possession Only License , filed by Long Island Power Authority (LIPA or the licensee), of November 4, 1993, complies with the , standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will be maintained in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i C. There is reasonable assurance (i) that the activities authorized by this license can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.C below); 1 D. The licensee is technically qualified to engage.in the activities authorized by this Possession Only License in accordance with the Commission's regulations set forth in 10 CFR Chapter I; j E. The licensee has satisfied the applicable provisions of ! 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Commission's regulations; F. The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public; l l l Page 1 of 3 Amendment 11 ! l I
A i G. After weighing the environmental, economic, technical, j and other benefits of the facility against environmental ! and other costs and considering available alternatives, the issuance of this amended Possession Only License No. NPF-82 is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied: and H. The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this i license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40, and 70. ;
- 2. Accordingly, Possession Only License No. NPF-82 is hereby !
amended in its entirety to read as follows: A. The license applies to the Shoreham Nuclear Power i Station, Unit 1, a former boiling water nuclear reactor j and associated equipment undergoing decommissioning, ! owned by the licensee. The facility is located in Suffolk County, New York, and is described in the Shoreham Defueled Safety Analysis Report (DSAR), and the Shoreham Environmental Report, as supplemented and ', amended. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Long Island ' Power Authority (LIPA or the licensee): (1) Pursuant to Section 103 of the Act and-10 CFR Part 50, to possess, use, but not operate the facility at the designated location in Suffolk County, New York, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for radiation monitoring equipment calibration in amounts as required; (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and , Page 2 of 3 Amendment 11
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(4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and , special nuclear materials as may have previously. [ been produced by the operation of the facility. C. This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations ' set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations (except for those exemptions from specific , portions of the regulations, previously granted by the Commission, and are still applicable), and orders of the Commission now or hereafter in effect and is subject to the additional conditions specified or incorporated below: (1) Licensee Certification of Post-Fuel Condition i Regardless of the issue and approval date of this license Amendment No. 11, the effective date of this amendment shall be the date the licensee provides certification that all special nuclear - material as irradiated fuel has been permanently removed from the site. D. The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall ;
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require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability [ claims. E. This license shall expire at midnight on April 13, 2013.
- 3. This license amendment will become effective as of the date the licensee provides certification that the irradiated fuel has been permanently removed from the site. I t
FOR THE NUCLEAR REGULATORY COMMISSION f Date of Issuance: i Page 3 of 3 Amendment 11
Enclosure 2 kl 6Y NUREG-13
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TECHNICAL SPECIFICATIONS I Shoreham Nuclear Power Station, Unit No. I r ocket No. 50-322 Ap ndix "A" to Lice se No. NPF-82 June 1 '1991
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Issued by the U.S. Nuclear Regulatory Comission Office of Nuclear React Regulation l
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!- INDEX DE ITIONS ' s SECTION AGE . 1.0 DEFINITIONS 1.1 ACTION......... ...................................... ......... 1-1 :, 1.2 CHANNEL CALIBRATIO ............................. ............. 1-1 1.3 CHANNEL CHECK.......... ..................... .................. 1-1 1.4 CHANNEL FUNCTIONAL TEST.... ............ ...................... 1-1 1.5 DEFUELED M0DE.................. .... ............................ 1-1 1.6 FREQUENCY NOTATION............. .. ............................ 1-2 1.7 FUEL H ANDL IN G OP E R ATIO NS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 -2 1.8 MEMBER ( S ) 0 F THE PUBL I . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1-2 1.9 0FFSITE DOSE CALCU ION MAN UAL (0D CM) . . . . . . . . . . . . . . . . . . . . . . . . . 1 -2 1.10 OPERABLE - OP BILITY............................. ............ 1-3 1.11 PROCESS C iTROL PROGRAM (PCP).......................... ........ 1-3 1.12 REPOP iBLE EVENT.......................................... .... 1-3 1.13 E B0UNDARY................................................. . 1-3 4 UNRESTRICTED AREA................................................ 3 i
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!- INDEX LIMIT NG CONDITIONS FOR FUEL HANDLING OPERATION & SURVEILLANCE REQUIREMENT SECTION PAGE 2.0 SAFETY L'1 ITS AND LIMITING SAFETY SYSTEM SETTINGS T USED). 2-1 3/4.0 APPLICABILIT ................................ ........ 3/4 0-1 .
3/4.1 INSTRUMENTATION ; 3/4.1.1 MONITORING INSTRUMEN ON Radiation Monitoring Ins umentati i.................... 3/4'l-1 ] Seismic Monitoring Instrumen on...................... 3/4 1-4 Meteorological Monitoring nstru ntation............... 3/4 1-7 3/4.2 CONTAINMENT SYSTEMS T USED)...... .................. 3/4 2-1 3/4.3 PLANT SYSTEMS-3/4.3.1 SEALED SOURC 0NTAMINATION................. ........... 3/4 3-1 3/4.3.2- SETTLEME OF REACTOR BUILDING Tota Settlement.................................... ... 3/4 3-3 , fferential Settlement Across The Structure............ 3/4 3-4 Penetra tion Dif ferent ial Se ttlement. . . . . . . . . . . . . . . . . . . . . 3 3-5 , t 3 .3.3 AREA TEMPERATURE M0NITORING.............................. 3/4 3 h SH05 A" - L'OT i 11 !
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OE.uiTE TA6G. INDEX Li TING CONDITIONS FOR FUEL HANDLING OPERATION & SURVEILL ANCE REQUIREMEN PAGE SECTIO : 3/4.4 LECTRICAL POWER SYSTEMS 3
..... 3/4 4-1 !
3/4.4.1 A. SOURCES..(DELETED) ...................... t WER DISTRIBUTION SYSTEMS..(DELETED) . ........ 3/4 4-2 e 3/4.4.2 ONSITE r l 3/4.5 FUEL HANDL G OPERATIONS i
...... ......... 3/4 5 1 ;
3/4.5.1 COMMUNICATIOr .................. i RM ......... ..... ........... 3/4 5-2 3/4.5.2 FUEL HANDLING PLA CRANE TRAVEL . . . . . . . .- ................ 3/4 5-4 3/4.5.3 ...... . AGE POOL . . . . . . . . . . . . . . . . 3/4 5-5 3/4.5.4 WATER LEVEL - SPENT FUEL S EL ORAGE POOL ........... 3/4 5 6 3/4.5.5 WATER CHEMISTRY - SPENT 3/4.6 RADIOACTIVE EFFLUENT { S ............... . .............. 3/4 6-1 3/4.6.1 LIQUID HOLDUP TA . BASES 3/4.0 APPLICABit ........................... .......... B 3/4 0-1 ! 3/4.1
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INSTRUMENTATION 3/4.1.1 MO ITORING INSTRUMENTATION adiation Monitoring instrumentation ...................... B 3/4 1-1 l Seismic Monitoring instrumentation ........................
/4 1-1
-1 Meteorological Monitoring instrumentation . . . . . . . . . . . . . . . . . . . . B 3/ f 4.2 CONTAINMENT SYSTEMS (NOT USED) ..................... B 3/4 2-1 i
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INDEX BAS PAGE SECTION 3/4.3 PLA SYSTEMS 3/4.3.1 SEALED RCE CONTAMINATION . . . . . . . . . . . . . .......... B 3/4 3-1 3/4.3.2 SETTLEMENT EACTOR BUILDING . . . . . . . ........... ... B 3/4 3-1 3/4.3.3 AREA TEMPERATUR ONITORING . . . . . . ................. B 3/4 3-1 3/4.4 ELECTRICAL POWER SYS S 3/4.4.1 A.C. SOURCES. . (DELETED) . . . ........................ B 3/4 4-1
.......... B 3/4 4-1 3/4.4.2 ONSITE POWER DISTRIBUTIO SYST iS. . (DELETED) 3/4.5 FUEL HANDLING OPER ONS COMMUNICATION .................... .............. B 3/4 5-1 3/4.5.1 .
3/4.5.2 FUEL HANDL1 o PL AT F O RM . . . . . . . . . . . . . . . . . .......... B 3/4 5-1 , 3/4.5.3 CRANE AVEL.............................. ...... B 3/4 5-1 : 3/4.5.4 W R LEVEL - SPENT FUEL STORAGE POOL . . . . . . . . . . . . . ... B 3/4 5-1
............ 3/4 5-1
. 3/4.5.5 VATER CHEMISTRY - SPENT FUEL STORAGE POOL 3/4.6 RADIO ACTIVE EFFLUENTS 3/ .1 LIQUID HOLDUP TANKS . .............................. B 3/4 6 i
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SECTION PAGE 5.1 SITE Exclusion Area.... ............................... ........... 5-1 Low Population Zone.... ....................... ................ 5-1 i SITE BOUNDARY for Radioact e Gaseous and quid Effluents.................}s ......... ....................... 5-1 5.2 FUEL AND CONTROL-ROD DATA Fuel Assemblies............... ...... ......................... 5-1 Contr ol Rod As semblies. . . . . . . . . . . . . . . . . . . .................... 5-1 5.3 !!ETEOR0 LOGICAL TOWER L TION................... ................ 5-1 , 5.4 FUEL STORAGE Criticality. .......................................... . . ' . . . . . 5-2 Drainag .................................................... ... 5-2 ; Ca ity........................................................ 5-2 i G JihAi, - viG 1 y .
l - I>EL6.TE PA66 INDEX ADM ISTRATIVE CONTR'OLS ,r r A PAGE SECTION
.... 6-1 6.1 RESPON BILITY................................................
....... 6-1 6.2 ORGANIZAT N...............................................
.......... 6-1 6.2.1 NUCLEAR RGANIZAT10N...............................
6-2 6.2.2 UNIT STAFF. .................................... ............. TIONS......................... ................ 6-2 6.3 UNIT STAFF QUALIFI 6-3 6.4 T RAI NIN G . . . . . . . . . . . . . . 6-3 6.5 REVIEW AND AUDIT......... ................. ...................... C)........ ......................... 6-3 6.5.1 SITE REVIEW COMMITTEE (
.... ............................ 6-3 FUNCTION...................
6-3 COMPOSITION.................. ............................... 6-3 ALTERNATES................ ...... ............................ 6-3 MEETING FREQUENCY...... ............ ......................... 6-4 QU0 RUM.............. .................. ...................... 6-4 RESPONSIBILITIES. ........................ ................... 6-5 , RECORDS....... .............................. ................ 6.5.2 INDEPENDENT (EVI EW PANEL (IRP) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 6-6 FUNCTION .......................................... ..........
....... 6-6 :
COMPO iT10N........................................... ; 6-6 ) HE ING FREQUENCY........................................ ....
. 6-7 00 RUM......................................................
-7 REVIEW........................................................ i I
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l I DEMTE PAGrE l t INDEX i admit TRATIVE CONTROLS i SECTION N PAGE NDENT REVIEW PANEL (IRP) (CONT'D) i 6.5.2 IND s AUDITS . ......................................... 6-7 RECORDS ... ...................... ............... 6-8 i
............... .................. 6-9 !
6.6 REPORTABLE EVENT ACTIO !
......... ..................... 6-9 l 6.7 . PROCEDURES AND PROGRAMS .
6.8 REPORTING REQUIREMENTS . . . . . . . ......... ............... 6-13 6.8.1 ROUTINE REPORTS . . . . . . . . . . ... .... ................... 6-13 ANNUAL REPORTS . . . . . . ......... ..................... 6-13 ANNUAL RADIOLOGICAL NVIRONMENTAL OPE TING REPORT . . . . . . . 6-13 , l ANNUAL RADIOACT E EFFLUENT RELEASE REPORT .............. 6-14 6.8.2 SPECIAL REPO ........... ............... .......... 6-14 ION ................................ ....... 6-14 6.9 RECORD RETE
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- 6.10 R ADI ATIQM PROTECTION PROGR AM . . . . . . . . . . . . . . . . . . . . . . . . .... 6-15 D 1 ATI O N A R E 4 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-16 6.11 HIG CESS CONTROL PROGAM (PCP) ............................. -17 6.12 6-1 ;
6 3 OFFSITE DOSE C ALCULATION M ANU AL (ODCM) . . . . . . . . . . . . . . . . . . . .
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DFi ETE PA6E. : 1
- INDEX i LIST OF FI L ~ -
FIGURE PAGE , i 5.1.1-1 EXCLUSION AREA............. ... ...................... 5-3 l
't 5.1.2-2 LOW POPULATIO. ........................... .......... 5-4 !
1 5.1.3-1 S 'NDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID : FFLUENTS.................................................. , f l i 1 1 i 1 t i l I t l l
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LIDT(OFTABLES 1
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TABLE . PAGE 1.1 RVE ILLANCE FREQUENCY NOT ATION. . . . . . . . . . . . . . . . . . . . 1-4 3.1.1.1-1 RADIA N MONITORING INSTRUMENTATION..... ........ 3/4 1 4.1.1.1-1 RADIATION . ITORING INSTRUMENTATIO RVEILLANCE REQUIREMENTS.. ................. ................ 3/4 1-3 , 3.1.1.2-1 SEISMIC MONITORING (STRUMEt 10N................. 3/4 1-5 . 4.1.1.2-1 SEISMIC MONITORING INS ENTATION SURVEILLANCE REQUIR . iTS.. ...................... 3/4 1-6 3.1.1.3-1 METEOROLOGICAL NITORING INSTR NTATION.......... 3/4 1-8 4.1.1.3-1 METEOROL F AL MONITORING INSTRUMENT ON SURVEI NCE REQUIREMENTS............... ......... 3/4 1-9 3.3.2.1-1 ITING VALUES OF SETTLEMENTS OF REACTOR UILDING(RB)................................... . 3/4 3-6 3.3.3.1- AREA TEMPERATURE MONITORING......................... 4 3-8 3.r.s.1-1 SPENT FUEL STORAGE POOL WATER CHEMISTRY............ 3/4 i l l 1 IHorIMA" UN:: 1x
DEMTE PA/ & i l 1.0 DE NITIONS The foll ng terms are defined so that uniform interpretation of th e specificati ns may be achieved. The defined terms appear in capita zed type and sha 1 be applicable throughout these Technical Specificat ons. ACTION 1.1 ACTION shall e that part cf a Specification which pres ibes remedial sneasures to be taken under designated conditions. CHANNEL CALIBRATION 1.2 A CHANNEL CALIBRATI shall be the adjustment, a necessary, of the channel output such t at it responds with the cessary range and accuracy to known valu of the parameter whi the channel monitors. The CHANNEL CALIBRATION hall encompass the tire channel including the senscr and alarm and r trip functions and shall include the CHAT;NEL FUNCTIONAL TEST. e CHANNEL CAL RATION may be perforrned by any series of sequential, o rlapping or total channel steps such that the entire channel is calibra ed. CHMiNEL CHECK 1.3 A CHAhfiEL CHECK shall be the qual tive assessment of channel behavior during operation by ob rva ion. This determination shall include, where possible, compa ison o the channel indication and/or status with other indicatione and/or s tus derived from independent instrument channels measuri the same p rameter. CHANilEL FUNCTIONAL TEST ; 1.4 /s CHANNEL FUNCTIONAL ST shall be:
- a. Analog channel - the injection of a simula ed signal into the channel as c se tu the sensor as practicabl to verify '
OPERABILITY including alarm and/or trip funct ns and channel failure tr ps.
- b. Bistabl channels - the injection of simulated si al into the senso to verify OPERABILITY including alarm and/c trip func ions.
The CH 4NEL FUNCTIONAL TEST may be performed by any seiies o seque tial, overlapping or total channel steps such that the . tire che iel is tested. DEFUE D MODE 1.E The plant is in the DEFUELED MODE when all fuel has been removed fr the reactor vessel and there is fuel in the spent fuel storage pool o in the new fuel storege vault. 5"0ZPT" L'T ! - 1-1 1
DELOe PAesE i 1 DE IITIONS ;! x , t FREQUE NOTATIONS 1.6 The FR ENCY NOTATION specified for the performance of Surve ante .i Require s shall correspond to the intervals defined in T e 1.1. j FUEL HANDLING OPE TIONS l 1.7 FUEL HANDLING OP TIONS shall be the movement of fu over or within the Spent Fuel Poo Suspension of FUEL HANDLING ERATIONS shall not ; preclude completion the movement of fuel to a afe conservative '! position. i MEMBER (S) 0F THE PUBLIC 'l 1.8 MEMBER (S) 0F THE PUBLIC shall -lude ' 1 persons who are not ; occupationally associated with tl p nt. This category does not include employees of the utility, contractors or vendors. Also- ! excluded from this category are rsu who enter the site to service , equipment or to make deliverie This tegcry does include persons who use portions of the site or recreat al, occupational or other 1 purposes not associated wi the plant. ! 0FFSITE DOSE CALCULATI0f; HAf L (ODCM) f 1.9 The OFFSITE DOSE CA ULATIO!I MANUAL (ODCM) shall c tain the . l methodology and r ameters used in the calculation o offsite doses , resulting fron dioactive gaseous and liquid effluent in the , calculation o gaseous and liquid effluent monitoring Al / Trip l Setpoints, 4d in the conduct of the Radiological Enviro tal j Monitorin rogram. The ODCM shall also contain (1) the Rad active ; Effluen Controls and Radiological Environmental Monitoring Pr rams requir d by Section 6.7.4 and (2) descriptions of the informatio that - sho d be included in the Annual Radiological Environmental Operat ! a Semiannual Radioactive Effluent Release Reports required by ! ecifications 6.8.1.3 and 6.8.1.4.
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.j- DEFIN ONS OPERABLE PERABILITY ;
1.10 A system, ubsystem, train, component or device shall be OPERA E or l have OPERA ITY when it is capable of performing its specif d function (s) d when all necessary attendant instrumentatii , controls, elec ical power, cooling or seal water, lubri ; ion or ! other auxiliary uipment that are required for the sy m, subsystem, '+ train, component o device to perform its function (s) re also capable of perfonning their latedsupportfunction(s). , PROCESS CONTROL' PROGRAM 1.11 The PROCESS CONTROL PROGR . PCP) shall cont n the current formulas, - sampling, analyses, tests, an determinati s to be made to ensure > that processing and packaging solid r ioactive wastes based on demonstrated processing of actua or s ulated wet solid wastes will l be accomplished in such a way as t a ure compliance with 10 CFR l Parts 20, 61, und 71 State regulat .5, burial ground requirements, , posal of solid radioactive and other requirements governing e waste. , REPORTABLE EVENT 1.12 A REPORTABLE EVENT shall e any of those condi ons specified in ! Section 50.73 to 10 CF Part 50. . SITE BOUNDARY 1.13 The SITE B0UNDAR shall be that line beyond which the 1 d is neither owr.ed, nor leas'ed, nor otherwise controlled by the licens . UNRESTRICTED AR RICTED AREA shall be any area at or beyond the SITE BOU ARY j 1.14 An UNR acce to which is not controlled by the licensee for purposes of pro ction of individuals from exposure to radiation and radioactiv erials, or any area within the SITE BOUNDARY used for residential uarters or for industrial, commercial, institutional and/or retreational purposes. , -1 l l l m=> =T: 1-3 ! _ __ . _ ~, . .
DELE.TE PAfrE i .g DEk)tITIONS x , TABLE-1.1 SURVEILLANCE FREQUENCY NOTATION NOTATION FREQUENCY S At least once r 12 hours. D At least ce per 24 hours. W t1 st once once per 7 days. H ast once per 31 days. Q At leas nce per 92 days. SA At least onc er 184 days. ., A At least once pe 66 days. , R At least once per 18_ nths(550 days) N.A. Not applicable. Completed prior to each reless h i l cunerunu _ tvu7v 7 14
f del ETE. 7%6E. . i i-f 9 SECTION 2.0 5 TY LIMITS. , 4D 1 LIMITING SAFETY TEM SETTINGS (N USED) i l 1 i l l l 2-1 ,
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I SECTIONS 3.0 and 4.0 LIMI G CONDITIONS FOR OPE TION AND ; SURVEI NCE REQUI MENTS 0
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i ( b'.TY d { 3/4 APPLICABILITY 1.IMITI CONDITION FOR FUEL HANDLING OPERATION 3.0.1 Comp ance with the Limiting Conditions contained in the s cceeding Specification is required during the DEFUELED MODE specified t rein; except that up failure to meet the Limiting Conditions the a ociated ACTION requirem ts shall be met. 3.0 ? Noncomplian with a Specification shall exist wher he requirements of tne Limiting Con ' tion and associated ACTION require ts are not met within the specified me intervals. If the Limiting C dition is restored prior to expiration of he specified time intervals, mpletion of the ACTION requirements is n t required. 3.0.3 Comencement or cont untion of FUEL HANDL: G OPERATIONS shall not be made when the conditions r the Limiting Con itions are not met and the associated ACTION requires su ension of FUEL (DLING OPERATIONS if they are not met within a specified ime interval. FUEL HANDLING OPERATIONS may be made in accordance with the A ION requir ents when conformance tu them:
- 1. Permits continued FUEL HAN It OPERATIONS for an unlimited period of time, or
- 2. Permits fuel to be moved a s fe, conservative position.
SURVEILLANCE REQUIREMENTS , , 4.0.1 Surveillance Require ts shall be met du ng the DEFUELED MODE or other APPLICABILITY condit' ns specified for indh ' dual Limiting Conditions. 4.0.2 Each Surveillan Requirement shall be performe within the specified surveillonc interval with a maximum allowabl extension not to exceed 25% of the s cified surveillance interval. 4.0.3 Failure to perform a Surveillance Requirement within he allowed surveillance in rval, defined by Specification 4.0.2, shall onstitute noncompliance th the OPERABILITY requirements for a Limiting ondition. The time limi s of the ACTION requirements are applicable at th time it is identified at a Surveillance Requirement has not been performe
. Surveillan e Requirements do not have to be performed on inoperabl equipmen 4.0.4 UEL HANDLING OPERATIONS shall not occur or continue unless all Surv 11ance Requirement (s) associated with the Limiting Conditions hav bee performed within the applicable surveillance interval. This provisi sb 11 not prevent passage through or to conditions as required to comply th ACTION requirements.
C " 0 " ' "1 L"::T - 3/4 0-1
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.1 INSTRUMENTATION 3/4 MONITORING INSTRUMENTATION 3/4.1.1. ADIATION MONITORING INSTRUMENTATION LIMITING CON N FOR FUEL HANDLING OPERATION 3.1.1.1 The radiat n monitoring instrumentation cha is shown in Table 3.1.1.1-1 shall be OP BLE with their alarm / trip s oints within the ;
specified limits. APPLICABILITY: DEFUELED M0 ACTION:
- a. With an Area Monitor instr ntation channel alarm / trip setpoint exceeding the value shown n able 3.1.1.1-1, adjust the setpoint to within the limit wit n4h rs or declare the channel inoperable.
- b. With the required ,onitor inoperable, ssure a portable continuous moni r with the same alarm tpoint is OPERABLE in the vicinity the installed monitor du ' g any fuel movement.
If no fuel vement is being made, perform ea surveys of the monitore red with portable monitoring instr entation at least once p. 24 hours. SURVEILLANCE .QUIREMENTS
/ \
4.1.1. Each of the above required radiation menstoring instrument ion chan s shall be demonstrated OPERABLE by the performance of the CHA L CHr ,, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for t riditions and at the frequencies shnwn in Table 4.1.1.1-1. 9 SHO"IHf" L'N!T 1 3/4 1-1
QQT M bb TABLE 3.1.1.1-1 IATION MONITORING INSTRUMENTATION MUM CHA LARM MEASUREMEKT INSTRUMENTATION OPERABL SETPOINT. RANGE.
- 1. Area Monitors
- a. Criticality Monitors
.1 4
- 1) Ne uel Storage 2** 5 20 mR/hr 10 to mR/hr ault !
.1 3
- 2) Spent Fuel 2** s 20 mR/hr 10 to 10 mR/hr [
Storage Pool , F t
***';;; ' u; ;7;;; 27; ;;r,it;7;d b3 th; ;;;; tu; d;t;;t:7 ;. -SiiO^0.L LNIT 1 3/4 1-2 i
l
)dL6.N M ,
.g TABLE 4.1.1.1-1 RADIATION N .. RING INSTRUMENTATION SURVEILLANC QUIREMENTS C EL C 'E L NCTIONAL CHANNEL INSTRUMENTATION CHE TEST CALIBRATION
- 1. Area Monitors
- a. Criticality Mo rs
- 1) New el Storage S* M Q t
- 2) Spent Fuel S* M Q Storage Poul
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i
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i e F EN5 55h 54 h dE I d Mg I T' WW ** '
= 5"Cri :A. - UiG 7 1 3/4 1-3 1
Y j IN EUMENTATION 3 /4.1 SEISMIC MONITORING INSTRUMENTATION LIMITING C DITION FOR FUEL HANDLING OPERATION 3.1.1.2.1 Th mic monitoring instrumentation shown in Ta e 3.1.1.2-1 shall be OPERABLE. APPLICABILITY. 'l MODE ACTION:
- a. With one or more of t above requir seismic monitoring instruments inoperable r more th 30 days, prepare and submit a Special Report +he .issi pursuant to Specification 6.8.2 within the 10 da t11ning the cause of the malfunction and . .sans fo estoring the instrument (s) to OPERABLE status. ;
i SURVElliANCE REQUIREMENTS , 4.1.1.2.1 Each of the abov required seismic moni ring instruments shall be demonstrated OPERABLE the performance of the C NNEL CHECK, CHANNEL FUNCTIONAL TEST, and C "~' CALIBRATION operations at he frequencies shown in Table 4.1.1 -1. 4.1.1.2.2 Each the above required seismic monitoring ins uments actubted durin a seismic event greater than or equal to 0.01 shall be restored to RABLE status within 24 hours and a CHANNEL CALIBP ION performed thin 5 days following the seismic event. Data shall b retrieve from actuated instruments and analyzed to determine the ma itude i of the ibratory ground motion. A Special Report shall be prepared an subm ted to the Commission pursuant to Specification 6.8.2 within 10 day de ribing the magnitude, frequency spectrum, and resultant effect upon i ation features important to safety. l l l l l l l l mnerum _ imTT 1 3/4 1 4
TE.LG_TE. TA6a + TABLE 3.1.1.2-1 SEISMIC MONITORING INSTRUMENTATION IMUM MEASUREMENT STRUMENTS INSTRUMENTS AND SENSOR CATION RANGE OPERABLE
- 1. Triaxial Time-History Accelerographs
- a. Primary Containment Mat, utside 0. -1 g 1 and adjacent to primary conteineent wall
- b. Outside Primary Containment Wa 0.01-1 g 1 E'. 131'-7"
- c. Free Field O. -1 g 1
- 2. Triaxial Seismic Switch
- a. Primary Contai .ent Mat 0.01 g 1*
- 3. Triaxial Respo e-Spectrum Recorders 0.01-2 g *
- a. Co einment Hut El 8'-0"
- b. Reactor Pedestal Wall - El 70'-8" 0.01-2 g 1 4
r A $ Y Af$i Y f E V- Yl1 Y fe V T> ?b i n. su 20,am - m. T1 3/4 1-5 ,
DEC 6TE. pat =G. TABLE 4.1.1.2-1 EISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENT CHANNEL CHANNEL FUNCTIONA CHANNEL INSTRUMENT AND SE R LOCATIONS CHECK TEST CALIBRATION
- 1. Triaxial Time-His y Accelerographs
- a. Primary Containme Mat, outside and adjacen o primary containment wa M* SA R
- b. Outside Primary Containmen Wall - El 131'-7" M* SA R
- c. Free Field SA R
- 2. Triaxici Seismic S- ches
- a. Primary ntainment Mat ** M R
- 3. Triaxia esponse-Spectrum Recorders
- a. Containment Mat El 8'-0"** M SA R
- b. Reactor Pedestal Wall N.A. N.A. R El 70'-8" l
i i l _ *Evcept seir-4c t-4;;er-
= .lith r;;;tur Ocr.t re' roer indiretiens = !MOREPl? - U"!T ' 3/4 1-6 l
MM Mbb UMENTATION 3/4. METEOROLOGICAL MONITORING INSTRUMENTATION LIMITIt:G C ION FOR FUEL HANDLING OPEPATION
~ 1 3.1.1.3.1 The meteo logical monitoring instrumentatio annels on the 400-ft tower shown in le 3.1.1.3-1 shall be OPERA .
APPLICABILITY: DEFUELED MOD ACTION:
- a. With one or more meteorol c monitoring instrumentation channels inoperable for - re tha days, prepare and submit a Specihl Report to th ommission pu ant to Specification 6.8.2 within the next 1 ays cutlining the se of the malfunction and the plans restcring the instrumen tion to OPERABLE status.
SURVEILLANCE RE ' EMENTS
' x 4.1.1. 3.1 ach of the above required meteorological monitoring instru ;tation channels shall be demonstrated OPERABLE by the perfo ce :
of CHAT't:EL CHECK and CHANNEL CALIBRATION operations at the frequenci wn ir. Table 4.1.1.3-1.
/
1 I e f
- ;UCCD'J " - :T : - 3/4 1-7
P6t ETE PACd TABLE 3.1.1.3-1 ETEOR0 LOGICAL MONITORING INSTRUMENTAT ; MINIMUM INSTRUMENTS INSTRUMENT OPERABLE
- 1. Wind Speed 1 Elev. 33 ft or Elev. 15
- 2. Wind Direction 1 Elev. 33 or Elev. 150 ft
- 3. A1 emperature Difference between 1 Elev. 33/150 ft 1
0 l I I i
-5l:0!'E!:Att U:!T : 3/4 1-8 ;
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i
% d ( EE. I TABLE 4.1.1.3-1 METEOR ICAL MONITORING INSTRUMENTATION SURVEILLANC QUIREMENTS i i
CHANNEL CHANNEL , INSTRUMENT CH , CALIBRATION
- 1. Wind Speed ;
Elev. 33 ft and Elev.150 ft D SA
- 2. Wind Direction Elev. 33 ft and ev. 150 ft D SA ,
l
- 3. Air Temp ure Difference between E . 33/150 ft D 5"0n:"lJ' L'r:T 1 3/4 1-9
- c. , . . . - . -.
A TEt.crv PA6E ,
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4.3 PLANT SYSTEMS , 3/4\1 SEALED SOURCE CONTAMINATION LIMITI CONDITION FOR FUEL HANDLING OPERATION , s 3.3.1.1 Ea sealed source containing radioactive material either n excess of 10 .icrocuries of beta and/or gamma emitting material r5 microcuriesof\1phaemittingmaterialshallbefreeofgreater han , or equal to 0.00 microcurie of removable contamination. APPLICABILITY: At 1 times. ACTION: With a sealed source havin removable contamination n excess of the above limit, withdraw the s led source f rom use d either:
- 1. Decontaminate and re ir the sealed urce, or
- 2. Dispuse of the sealed so ce in a ordance with Commission Regulations.
SURVEILLANCE REOUIREMENTS
, x 4.3.1.1 Test Requirements - Each s led so ce shall be tested for leakage and/or contemination by:
- a. '.e licensee, or
- b. Other persons s cifically authorized by he Comission or an Agreement S te.
The test method shal ave a detection sensitivity of a least 0.005 microcurie per test ample. 4.3.1.2 Test Fr uencies - Each category of sealed sources, ciuding startup source end fission detectors previously subjected to ore flux, shall tested at the frequency described below. -
- a. ources in use - tit least once per six months for all se ed sources containing radioactive material:
- 1. With a half-life greater than 30 days, excluding Hydrogen 3, and
- 2. In any form other than gas.
T C L". - UNIT 1 3/4 3-1
$ kN N '
4- PLANT EMS SURVEILLAN UIREMENTS (Continued)
- b. Storedsou$batnotinuse-Eachsealedsour and fission 1
~ detector shall tested prior to use or nsfer to another licensee unless te d within the prev s 6 months. Sealed '
sources and fission ctors trans red without a certificate indicating t last t date shall be tested prior to being placed into u i
- c. Startup sources and fi on detect - Each sealed startup source and fission ector shall be ted within 31 days '
following repair maintenance to the s e. 4.3.1.3 Reports - eport shall be prepared and submitt to the Commission on an nual basis if sealed source or fission de tor . leakage tests veal the presence of greater than or equal to 0. ' microcurie removable contamination. b 1 1 i . c iMORE"f? L'P!' 1 3/4 3-2
Eam M6E i PL T SYSTEMS 3/4. SETTLEMENT OF REACTOR BUILDING TOTAL SE MENT LIMITING C0h ION FOR FUEL HANDLING OPERATION
~ z 3.3.2.1 The total ettlenent of the Reactor Building s 11 not exceed 4.0 inches (80% of t limiting value specified in Ta e3.3.2.1-1).
APPLICABILITY: DEFUELED DE ACTION: With the total settlement of th Reactor B ding reaching 4.0 inches (80% of the limiting settlement v ue sp fiedinTable3.3.2.1-1), conduct an eng;neering review of fi d nditions and evaluate the consequences of additional settlement Submit a Special Report to the Commission pursuant to Specificatio 6. 2 within 30 days, containing the results of the investigation, e eva ation of existing and possible continued settlement, d the rem ial action to be taken, if any, including the date of th text survey. SURVE!LLANCE REQUIREMENTS , 1 4.3.2.1 The total se ement of the Reactor Building hall be determined to the n est 0.01 foot by measurement and lculation:
- a. At lea once every 6 months
- 1. Until observed settlement has stabilized *, and
. Whenever previously stabilized
- settlerent exceeds 10 inch since the previous reading.
. At least once every 24 conths thereaf ter. - ^0.10 usl, fi v.o y,m,ivua . . J nig . - 2:Crl"" 'a::' 1 3/4 3-3
T>Et 6TE PA6s 7 NT SYSTEMS DIF NTIAL SETTLEMENT ACROSS THE STRUCTURE LIMITIN ONDITION FOR FUEL HANDLING OPERATION s 3.3.2.2 The 'fferential settlement across the Reactor Bui g shall not exceed 1.6 ches (80% of the limiting value specifie n Table 3.3.2.1-1). APPLICABILITY: DEFUEL MODE ACTION: With the differential settlem t across the R ctor Building exceeding 1.6 inches (80% of the allowab settlement lue specified in Table 3.3.2.1-1), ccnduct an engineerin review field conditions and evaluete the consequences of addit al ttlement. Submit a Special Report to the Commission pursuant to cification 6.8.2 within 30 days, cor.taining the results of the i tigation, the evaluation of existing and possible continued set eme and the remedial action to be taken, if any, including the d e of th ext survey. SURVEILLANCE REQUIREMENTS
, x 4.3.2.2 The differentia settlement across the React Building shall be cletermined to the n rest 0.01 foot by measurement a calculation:
- a. At least cry 6 months
- 1. itil observed settlement has stabilized *, and -
- 2. Whenever previously stabilized
- settlement exceeds 0 inch since the previous reading, b At least once every 24 months thereafter. ;
1 l l l
*C.1 " 2 'r= pr::h = ra db.g.
- Oma""" L'rF 2 3/4 3-4
i 1 E l LANT SYSTEMS PE RATION DIFFERENTIAL SETTLEMENT - STRUCTURE TO SOIL LIMIT CONDITION FOR FUEL HANDLING OPERATION , s , I 3.3.2.3 The enetration differential settlement - structure t scil shall not exce 0.70 inch (80% of the limiting value specif d in Table 3.3.2.1-1). APPLICABILITY: DEFUE MODE ACTION: With the penetration differe tal settlement - ucture to soil exceeding 0.70 inch (80% of th allowable set ement value specified inTable3.3.2.1-1),conductan ineering view of field conditions and evaluate the consequences of a itiona settlement. Submit a Special Repcrt to the Corrnission pur an to Specification 6.8.2 within 30 days, containing the results f the investigotion, the evaluation of existing and possible nt ved settlement, and the ; remedial action to be taken, if any inclu ng the date of the next survey. , I SURVEILLA!!CE REQUIREtlENTS
- x ;
4.3.2.3 The penetratic different161 settlement - stru ure to soil sh611 be determined t the nearest 0.01 foot by nieasureme t and calculation.
- a. At le- once every 6 months.
- 1. Until observed settlement has stabilized *, and .
- 2. Whenever previously stabilized
- settlenent exceeds 0.10 inch since the previous reading.
- b. At least once every 24 months thereafter.
. *0.10 4r:ch fre" pre"4eus W ir;_ - - 500Til%" - UN:T 1 3/4 3-5
PA GE-D E L F_ . T E TABLE 3.3.2.1-1 LI
- NG VALUES OF SETTLEMENTS OF REACTOR BUILDING ,
LIMI VALUE SETTLEMENT inches)
- 1. Total 6bsolute settlement 5.0
- 2. Differential settlement acros -i RB (Tilt) 2.0
- 3. Penetration diffe ial settlement (between stre re to soil for e different settlement of burie pes) 0.9 f
.cunerure _ ne:T 1 : 3/4 3-6
D6 LE.TE PA66 PL 'T SYSTEMS 3/4.3 AREA TEMPERATURE MONITORING LIMITING ITION FOR FUEL HANDLING OPERATION
~ 1 3.3.3.1 The tem rature of each area shown in Table 3.3.3.1-1 all be maintained with the limits indicated.
APPLICABILITY: DEFUEL MODE, whenever the equipment in n affected area is required to be O RABLE. ACTION: With one or more areas exceeding e temperat limit (s) shown in Table 3.3.3.1-1:
- a. For more than 8 hours, in lie of any report required by Specification 6.8.1, prepar an submit a Special Report to the Comission pursuant t Speci ation 6.8.2 within the next 30 days providing record of e amount by which and the cumulative time t temperature i the affet.ted area exceeded its limit ed an analysis to ,onstrate the continued OPERAB TY of the affected equ ment.
- b. By more than *F, in aedition to the Special epurt required a ve, within 4 hours either restore t area to within i temperature limit or declare the equip nt in the effect area inopereble.
SURVEILLAN REQUIREMENTS
- x 4.3. The temperature in each of the areas shown in Table 3.3.3.1-1 sh be determined to be within its limit at least once per 24 hours. /
G.CT.D;;J: - UN:T :. 3/4 3-7
l TM teTS PA(.6 i 1 i TABLE 3.3.3.1-1 , AREA TEMPERATURE MONITORING {
-l l
AREA TEP RATURE LIMIT ,
- a. Control Room 90
- b. Chiller Equipment Room ( 63') 104
- c. Relay Room 104
- d. Emergency Switchgear Rocms -
104 ,
- e. Battery Rooms 104
- f. Diesel Generator Roor 120 i
- g. Screenwell House 104 i
- h. Reactor Bui ng - Secondory Containment
- 1. Gener' Areas. 4
- 2. Ref ing Area 11
- 1. Re or Building - Primary Containment General Areas 150
. Area'Beneath RPV 150 ,
- 3. Drywell Head Area 185 i
1 5 t r SugeE* " "F!T 2 - 3/4 3-8
d 2 m b - r- -.. A 4 2 ! DELEtrE 'PA6E. l j 3/ ELECTRICAL POWER SYSTEMS - i 3/4.4. A.C. SOURCES l (DELETED) -! i
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- eunoru m u ' *"' ' 3/4 4-1
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' EL TRICAL POWER SYSTEMS -
3/4.4. ONSITE POWER DISTRIBUTION SYSTEMS , (DELETED j
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t t i f _ C::0. " I: '"" UN:' * --- 3/4 4-2 ^-_"---"-_m I h
4.5 FUEL HANDLING OPERATIONS 3/4 COMMUNICATIONS L1HITING ITION FOR FUEL HANDLING OPERATION
~ /
3.5.1.1 Direct c nication shall be maintained between t control room and fuel handlin ersonnel. APPLICABILITY: DEFUELED M , whenever handling ir diated fuel. ACTION: Whtn direct ccrconication between the rol room and fuel handling personnel cannot be maintained, imme ate suspend handling of irrodiated fuel. SURVEILLANCE REOUIREMEt 1 x 4.5.1.1 Direct mmunication between the control room and fue handling per nel shall be demonstrated within one hour prior t he start of at least once per 12 hours during h6ndling of irradiat , fuel. e 7 SUCC UA:. - U;GT 1 3/4 5-1 b
l UEL HANDLING OPERATIONS 3 .2 FUEL HANDLING PLATFORM LIMITI CONDITION FOR FUEL HANDLING OPERATION ,
~
3.5.2.1 The el handling platform shall be OPEPABLE when us for 4 handling fuel control rods within the Spent Fuel Storage ool. i APPLICABILITY: DE LED MODE, during handling of fuel semblies or I control rods. l 1 ACTION: With the requirements for the uel handling p tform OPERABILITY not satisfied, suspei.d use of any serable fu handling platform equipment from operations involvi, the h dling of control rods and fuel assemblies after placing the 1 d a safe condition. , SURVEILLANCE REQUIREMENTS 1 x 4.6.2.1 Each fuel hendling atform crane or ist used for handling of control rods or fuel as mblies shall be deno trated OPERABLE within 7 days prior to t start of such operation with that crane or hoist by:
- a. Demonstr ing the operation of the uptravel ne anical cutoff n the frame muunted and monorail hoists en uptr el brir.gs the top of the fuel assembly to 2 et below th iormal fuel storage pool water level,
- b. emonstrating operation of the slack cable cutoff on the main hoist when the load is less than 50 + 25 pounds. '
- 5"0C0ll" - L' NIT 3/4 5-2
DELATE. PA6til S EILLANCE REQUIREMENTS (Continued) ,
- s
- c. Demonstrating operation of the loaded interlock on the m n ist when the load exceeds 485 1 50 pounds.
- d. Ue. strating operation of the loaded interlock on t auxil ry hoist when the loud exceeds 400 1 50 poun .
b l s0"m?R "'T I - 3/4 5-3 1
K / CT'E
"$)A M UEL HANDLING OPERATIONS 3/ .3 CRANE TRAVEL LIMITI CONDITION FOR FUEL HANDLING OPERATION ,
3.5.3.1 Loa in excess of 1200 pounds shall be prohibited fro travel over th spent fuel storage pool racks with fuel asse ies in the spent fuel s rage pool racks and the spent fuel shippi cask movement shall be ohibited from travel over the refuelin floor except when moved by he OPERABLE polar crane. APPLICABILITY: DEFUELED ODE ACTION: With the requirements of the abo specificati not satisfied, place the trane load in a safe condition. SURVEILLANCE REQUIREMENiS x1 4.5.3.1 The polar crane shall be demo tra d OPERABLE:
- a. Within 7 days prior to a at least ce per 7 days during movement of loads in ex ss of 1200 po ds over the spent fuel storage pool rac or movement of t spent fuel shipping c6sk over t e refueling floor by:
- 1. Verifying t redundancy of the crane bra s, gear trains, re ing systera, and load attaching ints by visual i pection.
- 2. Demon rating OPERABILITY of the crane interlocks lim switches, alarms and fail safe control compon ts by unctional test.
- 3. erformance of a wire rope inspection in accordance with ANSI B30.2, 1976. The wire rope shall be replaced should any of the replacement criteria of ANSI B30.2 be met.
i l l i I l l 4ll0":"A" - LJ T 1 3/4 5-4 i i
( 6M M6G F HANDLING OPERATIONS 3/4.5 ATER LEVEL - SPENT FUEL STORAGE POOL LIMITING C ION FOR FUEL HANDLING OPERATION x - 3.5.4.1 At least feet of water shall be maintained o r the top of irradiated fuel assem ies seated in the spent fuel s age pool ra cks. APPLIC ABILITY: DEFUELED MOD ACTION: With the requirements of the above sp ication not satisfied, suspend all movement of fuel assemb' es a crane operations with loads in the spent fuel storage 1 crea a r placing the fuel assemblies and crane load in e afe conoition. estore level within 8 hours ur prepare 6 report t he NRC pursuant to ecification 6.8.2 within the next 10 days. SURVEILLANCE REQUIREP TS x 4.5.4.1 The wa r level in the spent fuel storage pool shall determined t e at least at its minimum required depth at least ce per 7 days
- SHOP.Eu." - U'2 T 1 3/4 5-5
MIM bh d FU. ANDLING OPERATIONS 3 /4.5. ER CHEMISTRY - SPENT FUEL STORAGE POOL LIMITING CON (ON FOR FUEL HANDLING OPERATION ,
~
3.5.5.1 The spent t storage pool water chemistry shal e maintoined within the {17 its specified in Table 3.5.5. . APPLICABILITY: DEFUELED MODE ACTION: With any one or more of the water che y limits exceeded, initiate action within 72 hcurs to restore t wate chemistry to within limits and conduct an evaluation to det .ine cause. SURVEILLANCE REQUIREMENT ~ 4.5.5.1 The spen uel storage pool water chemistry shall determined to b within the limits by analysis of those param rs et the frequent s specified in Table 3.5.5.1-1.
;lCTI:'l". - L' NIT 1 3/4 5-6
l
' s'.,,s %dTE Mbb l i
l TABLE 3.5.5.1-1 i SPENT FUEL STORAGE POOL WATER CHEMISTRY PARAMETER ANALYSIS + FREQUENCY. Chloride 5 ppm MONTHLY Conductivity i 10 micro mhos/cm 925' MONTHLY , pH 5.3 s pH $ 8.6 HLY p 1 I
.i EM0". ".?".- L'MIT 1 - 3/4 5-7 7 .,
y . - - . ,
~ N' 571E. PMrdiL 3 6 RADI0 ACTIVE EFFLUENTS 3/4.6 LIQUID HOLDUP TANKS LIMITING C TION FOR FUEL HANDLING OPERATION
~ 1 3.6.1.1 The qua ty of radioactive material contained i ach outside temporary ta shall be limited to less than or ual to 10 curies, excluding trit and dissolved or entrained le gases.
APPLICABILITY: AT ALL TIME
- ACTION: i With the quantity of radioactive mat in any outside temporary tank exceeding the above limit, imme ly suspend all additiens of radioactive material to the tank a with 48 hours reduce the tank contents to within the limit, an describe events leading to this ,
condition in the next Semiann Radioactive luent Release Report. ; SURVEILLANCE REQUIREME s 4.6.1.1 The qua ty of radioactive material contained in ch outside tempor . tank shall be determined to be within the a ve ^ limit by ana zing a representative sample of the tank's conten at least onc er 7 days when radioactive materials are being added the tan i 1 f i I t 0!!On:!"" '3T' 1 3/4 6-1
g wrE.PA(sE I
'i ASES FOR SECTIONS .0 AND 4.0 ;
LIf11 TING CONDITIONS FOR HANDLING OPERATION A SURVEILLAt E REQUIR ENTS i l V
i 4
^
; v l
l l l l l 1 NOTE The BASES contained i succe ing pages sumarize the reasons for the Spe ifi tions in Section 3.0 and 4.0, but in accordan with 10 CFR 50.36 are not part of these Techni Specification. k l l j i I i
.)
. 1 DF.LETG PA&E- l 3 .0 APPLICABILITY l BAS <
1 The ecifications of this section provide the general requiremen applicable to each of the Limiting Conditions for Fuel Handl1 Operation and Surveillance Requirements within Se ion 3/4 3.0.1 This ection states the applic6b111ty of each specification in t ms of the specified condition and is ' ovided to delineate specifica when each specification is applic le. The ACTION requir nts establish those remedial asures that must be taken within spe ified time limits when the equirerents of a Limiting Condition for Fu Hondling Operation are ot met. The spec.ified time limits of th ACTION requirements . e applicable from , the point in time there was failure to meet a imiting Condition for Fuel Handling Operation. The me limits of t ACTION requirements - are also applicable when a syst or componen is removed from service for surveillance testing or inves gation o operational problems. Individual specifications may inc1 e a sp cified time limit for the completion of a Surveillance Require. nt hen equipment is removed from service. In this case, the allo . e outage time limits of the ACTION requirarents are applicable wh his limit expires if the surveillance hos not been completed. Compliance with ACTION requir ments tha permit continued operations of fuel handling for unlimited riod of time provides an acceptable level of safety f r continued ope ation without regard to the status of the plant be re or after fuel ndling operations. Therefore, in this case fuel andling operations be made in accordor.ce with the provis ns of the ACTION requir lents. The provisions of this specif' cation should not, however, e interpreted as endorsing the failur- to exercise good practice in storing systems or components OPERABLE status before startin operations of fuel handling. 3.0.2 This s ecification defines those conditions nece ary to constitute comp 1 nce with the terms of an individual Limitin Condition for F 1 Handling Operation and associated ACTION requirement. 3.0.3 his specification provides that cormencement of fuel handling erotions must be made with the full complement of required systems, quipment or components OPERABLE per the requirer:ents of the Limiti Conditions for Fuel Handling Operation. he intent of this provision is to ensure that handling of irr dioted fuel is not initiated with eithr.r required equipment or s teris inoperable or other limits being f.xceeded. 1
- "CZ"n". L':.'r : B 3/4 0-1
. 4 DELEETE PA66 , i AP 1CABILITY BASE s , 4.0. This specification provides that surveillance activities cessary to ensure the Limiting Conditions for Fuel Handling Ope tion are met and will be performed during the cond ions for which the imiting Conditions for Fuel Handling Operation e applicable. Pr 'isions for additional surveillance activitie to be performed without egard to the 6pplicable conditions are pr vided in the individual Sur illance Requirements. . 4.0.2 The pr isions of this specification pro de allowable ' tolerances for performi surveillance activities bey d those specified in the nominal urveillance interval. The tolerances are necessary to provide opera ional flexibility becau . of scheduling and performance considerations. The phrase "at least" associated with a surveillance frequency does n negate this all able tolerance; instead, it permits the more f quent performa e of surveillance activities. 4.0.3 The provisions of th spe fication set forth the criteria for determination of complia ce ith the OPERABILITY requirements of the Limiting Condition for Fuel Handling Operation. Under this criteria, equipment, syste r components are assumed to be OPERABLE if the ossociated surve anc activities have been satisfactorily performed within th specif d time interval. Nothing in this provision is to be constr ed as defi ing equipment, systems or components OPERABLE, when such ems are foun or known to be inoperable although still meet ng the Surveilla e Requirements. This specification als clarifles that the AC ON requirements are applica:>1e when Surve' lance Requirements have t been completed within the allowed surve' lance interval and that the time limits of the ACTION requirement apply from the point the time is identified , that a surveillance h s not been performed and not at th time that the allowed surveil nce interval was exceeded. Completi of the Surveillance Requi ment within the allowable outage time 1 its of the ACTION requir ments restores compliance with the require mts of Specification 4 .3. However, this does not negate the fact t t the failure to hav performed the surveillance within the allowed surveillance nterval, defined by the provisions of Specification 4.0.2, was violation of the OPERABILITY requirements of a Limiti Condition or Fuel Handling Operation that is subject to enforcement action. urther, the failure to perform a surveillance within the provis ns of Specification 4.0.2 and not meeting the associated ACTIO requirements per Specification 3.0.1 is a violation of Tec ical Specification requirements and is, therefore, a reportable ev t under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is condition prohibited by the plant's Technical Specifications.
.SH0prFAH . WTT 1 B 3/4 0-2
f APP CABILITY BASE 5\ x 1 If the 110wable outage time limits of the ACTION require s are less than 4 hours, a 24-hcur allowance is provided to pe ta delay in implem ting the ACTION requirements. This provide an adequate time li 't to complete Surveillance Requirements t have not been perforned. The purpose of this allowance is to rmit the completion of a surv 11ance before a suspension of fue landling : would be required to c ply with ACTION requirements o before other renedial measures would required that may preclud the completion of a surveillance. The b is for this allowance i udes ' consideration for plant con tions, adequate plan ng, availability of personnel, the time required perform the sur 111ance, and the ! safety significance of the dela in completin he required surveillance. If a surveillance s not comp ted within the 24-hour , allowance, the time limits of the TION r irements are applicable at that time. When a surveillance i per rmed within the 24-hour allowance and the Surveillance Require ts are not met, the time limits of the ACTION requirements are licable at the time the surveillance is terminated. Surveillance Requirements do ot have to e performed on inopt;rable equipment because th ACTION requir ents define the remedici measures that apply, owever, the Sury 11ance Requirements have to be met to demonstrat that inoperable equ ient has been restored to OPERABLE status 4.0.4 This spe fication ensures that surveill ce activities associr.ted with Limiti Conditions for Fuel Handling Ope tion for handling irradiated el have been performed within the sp ified time interval prior to h diing irradiated fuel. The intent of t s provision is to e ure that surveillance activities have been satisfactorily ..onstrated or a current basis as required to me the OPERABILITY re irements of the Limiting Condition for Fuel Handi q Operation.
-SHOREHA b ONI-T-1 B 3/4 0 3
DELEE PA6G_ i 3/ 1 INSTRUMENTATION BASESx \ 1 3/4.1.1 ITORING INSTRUMENTATION 3/4.1.1.1 RAD TION MONITORING INSTRUMENTATION The OPERABIL of the radiation monitoring instrume ation ensures that: (1) e radiation levels are continually asured in the areas served by t individual channels; (2) the a rm or automatic action is ini oted when the radiation lev trip setpoint isexceeded;and(3)suf ient information is ava able on selected parameters to monitor and a ess these variables 11owing an accident. This capability 1 consistent with I CFR Part 20, 10 CFR Part 50, Appendix A, General D ign Criteria , 41, 60, 61, 63 and 64. 3/4.1.1.2 SEISMIC MONITORING INSTRUh TA ON The OPERABILITY of the seismic m i oring instrumentation ensures that sufficier.t capability is avail le t promptly determine the magnitude of a seismic event and e luate t response of those features important to safety. T s capabili is required to permit comparison of the measured res nse to that us in the design basis for the station. This instr .entation is consis nt with the recommendations of Regulato Guide 1.12 "Instrume ation for Earthquakes", April 1974. 3/4.1.1.3 METEOROLOGI L MONITORING INSTRUMENTATION The OPERABILIT of the meteorological monitoring inst -entation ensures that suff' ient meteorological data is available for estimating pute tal radiation doses to the public as a result f routine or ec dental release of radioactive materials to the atmosphere. he capability is required to evaluate the need for initiating rotective measures to protect the health and safety of public. is instrumentation is consistent with the recommendations of Regu tory Guide 1.23 "Onsite Meteorological Programs," February 1972.
- = ^I: A . - L :: ;- B 3/4 1-1
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. l LE 4 P E i r 3/4.2 CONTAINMENT SYSTEMS (NOT USED)
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P Y bd 3N.3 PLANT SYSTEMS BAS 3/4.3.1\EALEDSOURCECONTAMINATION The li tations on removable contamination for sources requi n f leak testing, including alpha emitters, is based on 10 CFR 70.3. c) g , limits for plu nium. This limitation will ensure .that leakag from : byproduct, sourc and special nuclear material sources will ot exceed allowable take values. Sealed sources are classif d into three groups accor g to their use, with surveillance re trements. ' commensurate with th probability of damage to a source that group. Those sources which ar frequently handled are require to be tested more often than those w ch are not. Sealed sources ich are cuntinuously enclosed wit 'n a shielded mechanism, e., sealed ; sources within radiation m itoring devices, are c sidered to be stored and need not be teste unless they are re ved from the shielded mechanism. 3/4.3.2 SETTLEMENT OF REACTOR B DING Total settlement of the Reacto uil ng con be uced as an indicator that ccnfirms the adequacy he underlying soils with i respect to liquefaction. Liquefaction f these sci's is considered , unlikely if the relative density exc ds 5%. Ther fore, measured ' settlements that are less than pred cted, suming the relative density of the underlying soils e als 65%, onfirm that the underlying soils are sufficienti dense so as to preclude liquefaction during the DBE. Difftrential settlemen across the Reactor B 1 ding would increase loads on piping c inected to the building . e to anchor point rota tion. The requireme s for measuring differenti settlement across the building ens es that ample opportunity for further , investigation and cor ctive action is provided if diff ential settlement approache the allowable value. Differential settlement between the Reactor Building an the soil would increase ads on the buried pipes that are connected t the i structure. Th requirement for measuring settlement of the Rea tor Building ens es that ample opportunity for further investigatio and ' corrective tion is provided if differential settlement between t structure nd the soil approaches the allowable value. i 3/4.3. AREA TEMPERATURE MONITORING The rea temperature limitations ensure that equipment will not be su etted to temperatures in excess of their environmental alification temperatures. Exposure to excessive temperatures may egrade equipment and can cause loss of its OPERABILITY. 1 0"O = "" *'!' I B 3/4 3-1
De Lett PAC 6 3/4. ELECTRICAL POWER SYSTEMS BASES 3/4.4.1 A 3/4.4.2 A.C. SOURCES AND ONSITE POWER DISTRIBUTION SY EMS (DELETED) U'"T i 8 3/4 4-1 1 ^- :ni ::: 'h.10 C H O P.E P ^ "
>ELETWE PA6E l 3 5 FUEL HANDLING OPERATIONS BASE ,
s 3/4.5.1 MMUNICATIONS The requ ement for communications capability ensures tha fuel handling rsonnel can be promptly informed of signific t changes in the f 111ty status. 3/4.5.2 FUEL HANDL G PLATFORM The OPERABILITY re irementsensurethat(1)th fuel handling platform will be used fo andling centrol rods an uel assenblies, and (2) each crane and hoi has sufficient load pacity for handling fuel assemblies and control ds. 3/4.5.3 CPANE TRAVEL The restriction on movement o loads n excess of the nominal weight of a fuel assembly over other u asserblies in the storage pool and of the spent fuel shipping ca over the refueling floor ensures that in the event the load i d ped (1) the activity release will be limited to that contained a si le fuel assembly, (2) any possible distortion of fuel in th storage eks will not result in a criticel array, and (3) the red idancy of co., nents assures the placement of the load in a saf condition. Th assumption is consistent with the activity elease assumed in e safety analysis. 3/4.5.4 WATER LEVEL - SP iT FUEL STORAGE POOL The restrictions n minimum water level ensure th- sufficient water depth is avail le to provide adequate shielding f the low burnup condition of the irradiated fuel assemblies. The m imum water depth is consiste with the assumptions of the safety anal is. 3/4.5.5 WATE HEMISTRY - SPENT FUEL STOPAGE POOL The mainter nce of spent fuel pool water chemistry ensures that degradati of the spent fuel assemblies and the spent fuel racks is minimiz . B 3/4 5-1
-SiteREHE - UiGT 1
i D6LETE PA66 ! , 3/4.6 RADIO VE EFFLUENTS BASES
~ r 3/4.6.1 LIQUID HOLDUP TANKS Restricting the quantity of radion material contained in the specified tanks provides assurance th n event of an uncontrolled release of the tanks' contents, t esulting entrations would be :
less than the limits of 10 CF rt 20, Appendix B, ble II, Column 2, at the nearest potable er supply and the nearest face water , i supply in on UNRESTRI AREA. i V
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- 5. DESIGN FEATURES 5.1 5 EXCLUSION EA 5.1.1 The ex usion area shall be as shown in Figure 5.1.1-1. f LOW POPULATION 2 5.1.2 The low popul ion zone shall be as shown in Figu 5.1.2-1 SITE BOUNDARY FOR RADIO. TIVE GASEOUS AND LIQUID EFFL NTS 5.1.3 The SITE BOUNDARY f radioactive gaseous d liquid effluents shall -
be as shown in Figure 5.1.3- , 5.2 FUEL AND CONTROL R0D DATA FUEL ASSEMBLIES 5.2.1 The spent fuel storage pool co ins 560 fuel assemblies with each fuel assembly containing 62 fuel rode a two water rods clad with Zircaloy-2. ; Each fuel rod is designed to have nomin active fuel length of 150 inches. ! The fuel has a maximum average e chment o 1.90 weight percent'U-235. CONTROL ROD ASSEMBLIES 5.2.2 There are 137 contr rod assemblies, each onsisting of a cruciform ! array of stainless steel ubes containing 143 inche of boron carbide, B 4C, powder surrounded by.a uciform shaped stainless st 1-sheath. 5.3 METEOROLOGICAL WER LOCATION { 5.3.1 The 400 f t meteorological tower is located as show on Figure 5.1,3-1.
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t $& D GN FEATURES l ~ 1 5.4 FD14, STORAGE i CRITICALIT , 5.4.1 The spent el storage racks are designed and shall b aintained ! with:
- a. A k,ff equi lent to less than or equal to 5 when flooded with unborated wate which includes a conser tive allowance of 1.0% l delta k/k for unc tainties as describ in Appendix 9A of the DSAR. ,
- b. A nominal 6 inches in ne directio and 9.25 inches in the other.
direction center-to-cen r dista e between fuel assemblies
- placed in the storage rac .
DRAINAGE 5.4.2 The spent fuel storage poo is design and shall be maintained to ; prevent inadvertent draining o the pool belo elevation 152'- 4 1/2". CAPACITY' 5.4.3 The spent fuel orage pool is designed and sh 1 be maintained with a storage capacity l' ited to no more than 2176 fuel as .blies. ; r t f i I 1 i
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SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS FIGURE 5.1.3-1 SHOREHAM - UNIT 1 5-5
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6.0 DMINISTRATIVE CONTROLS 6.1 R 00NSIBILITY e Resident Manager shall be responsible for the managemen of the 6.1.1 overall pla and ensuring the safe storage and handling of irradia d fuel. The R ident Manager shall delegate in writing the successi to this responsibility uring his absence. 6.1.2 The Wa h Engineer (or during his absence from the C ntrol Room a designated certifi d fuel handling operator) shall be respon isble for the effect, signed Control Room comman function. A management directive to by the Executive Vic President of Shoreham Project, shal be reissued to all l station personnel on a annual basis. 6.2 ORGANIZATION 6.2.1 Nuclear Organization An organization shall be estab ished for the un all in the DEFUELED MODE and include the positions for corporate management. This rganization for activities affecting the safe storage an handling of irradiated nuclear fuel.
- a. Lines of authority, respons b ity and communication shall be established and defined from he highest management levels through intermediate level t and including all organization positions involved with t sa storage and handling of irradiated fuel. These elation ips shall be documented and updated, as appropriat , in the f of organizational charts, functional descriptio s of departm tal responsibilities and relationships, and b descriptions r .key personnel positions, These requirements or in equivalent f rms of documentati shall be documen d in the DSAR and up ted in accordance with 10 CFR 50.71(e The Executiv Vice President of Shoreham P ject shall have l b.
corporate sponsibility for overall plant clear safety and shall tak any measures needed to ensure acte table performance of the waff in maintaining and providing tech calofsupport to irradiated the p1 t to ensure the safe storage and handli fuel Resident Manager shall be responsible for overa unit safety l
- c. T d shall have control over those onsite activities n cessary for safe maintenance of the plant and storage and handling if irradiated fuel.
The individuals who train the operations staff and those w carry out health physics and quality assurance functions may repo to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
" NIT 1- 6-1 - _ u n 7.:. : 2 . O - = TI =
DEL 4 hie PA6E.
\ADTNISTRATIVECONTROLS ,
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UNIT FF 6.2.2 T station organization shall be as follows:
- a. E h duty shift shall be composed of at least the mini shift er consisting of three operators, one of which shal be a Watch er. The Watch Engineer shall hold a Senior Fu Handling Engi Opera rs Certification
- on SNPS Unit 1.
- b. One of t operators, as specified in 6.2.2a, o ier than the Watch Eng eer shall be certified
- and qualif - to respond to any alarms in t Main Control Room. This opera 1 re should normally Spent Fuel Pool, be in the Ha Control Room when fuel is in
- c. All fuel hand 11 operations shall be ob rved and directly supervised by a rtified* operator or ndividual certified to supervise the han ing of irradiated el, and who has no other concurrent responsi lities during is operation.
- d. A Health Physics techn ian shall e on site when irradiated fuel is being handled on sit
- e. Adequate shift coverage sh ' be maintained without routine heavy use of overtime. The objec ve shall be to have operating personnel work a nomal 8- ou day , 40-hour week. However, in the event that unforesee prob ms require substantial amounts of overtime to be used, or during tended periods of fuel movement, major maintenance, or uajor unit dification, on a temporary basis the following uidelines sha be followed:
- 1. An individu should not be pem tied to work more than 16 hours stra ht, excluding shif t t never time.
- 2. An indi dual should not be pemitte to work more than 16 hours any 24-hour period, nor more han 24 hours in any 48-h r period, nor more than 72 hours n any 7-day period, all xcluding shift turnover time.
. 3. break of at least 8 hours should be allow d between work eriods, including shift turnover time. Any deviati i from the above guidelines shall be authorized b the Resident l Manager or his deputy, or higher levels of management. 6.3 UP STAFF QUALIFICATIONS 6.3. Each member of the unit staff shall meet or exceed the minimu - qu ifications of the programs and procedures as outlined in Section i ce
- Certification of personnel perfoming these functions shall be in accord with the licensee's NRC-approved certification program, i 6-2 Amendment No. 9 SHOREHAM - UNIT 1 ,
1 l D6t.E7G PA6E. j/ ADMI STRATIVE CONTROLS e l Conduct Operations **, of the Defueled Safety Analysis Report for compar ! positions. 6.4 TRAININ 6.4.1 A retrai ng and replacement training program for the stati , shall staff shall be maintai d under the direction of the Training Supervis meet or exceed the equirements of the programs and procedures s outlined in Section 13.2 - T ining Program, of the Defueled Safety An ysis Report. 6.5 REVIEW AND AUDIT 6.5.1 SITE REVIEW COMMI E (SRC) FUNCTION . 6.5.1.1 The SRC shall functio to advise the R ident Manager on all matters l related to nuclear safety.
, COMPOSITION 6.5.1.2 The SRC shall be composed of hairman or alternate chairman and six or more members or alternate memb of the plant staff as designated by the chairman.
ALTERNATES 6.5.1.3 All alternate member shall be appoin d in writing by the SRC Chairman; however, no more an two alternates all participate as voting members in SRC activities any one tire. , MEETING FREQUENCY 6.5.1.4 The SRC sh meet at least once per calendar onth and as convened by the SF Chairman or his designated alternate
** T . terms " operation" and " operations" as used herein refer actions by icensee personnel and utilization of Shoreham systems and equ ment to support activities which are required in the DEFUELED MODE or o er non-operating plant configuration, including, but not limited to, safe fuel storage and handling, radiological control, personnel habitab lity, facility maintenance, and decommissioning.
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i i EELETE PA64-AD NISTRATIVE CONTROLS r x QUORUh e quorum of the SRC necessary for the performance of the SR l 6.5.1.5 responsibi ty and authority provisions of these Technical Specificat' ns shall consis of the Chairman or his designated alternate and four her members inclu 'ng alternates. RESPONSIBILITIES r l 6.5.1.6 The SRC sh i be responsible for:
- a. Review of (1 all proposed procedures require y Specification 6.7 and change thereto, (2) all proposed pr rams required by Specification 6. and changes thereto, and any other proposed procedures or cha es thereto as determin by the Resident Manager l to affect nuclear s fety; ,
- b. Review of all propose tests and exp iments that affect nuclear ,
safety;
- c. Review of all proposed cha es the Possession Only License and to Appendix A Technical Spec f cations;
- d. Review of all proposed cha es r modifications to unit systems ,
or equipment that affect uclear afety;
- e. Investigation of all < olations of e Technical Specifications, including the prepar tion and forwar ng of reports covering evaluation and rec ...mendations to prev t recurrence, to the Executive Vice Pr sident of Shoreham Pr ect; l
- f. Review of all EPORTABLE EVENTS;
- g. Review of ation operations to detect potent 1 hazards to ,
nuclear fety;
- h. Perfo ,. ante of special reviews, investigations, or nalyses and rep ts thereon as requested by the Resident Manage l i.
view of the Security Plan and implementing procedure
- j. Review of the Emergency Plan and implementing procedures; Review of the Fire Protection Plan and implementing procedur ;
6-4 A..m. a m. .i. :c. O
- 20T.0 = ",OT= 1
D E 4. g i g P A (r E. ADMI STRATIVE CONTROLS
- 1. Review of the proposed changes to the Process Control Program PCP);
Re ew of the proposed changes to the Offsite Dose Calcul ion m. Manu (0DCM); the proposed Major Changes to Radioactive ste
- n. Review Systems;
- o. Review of Pe onnel Radiation Records annually " determine how exposures migh be lowered consistent with AL A principles.
Document such c siderations;
- p. Review of any acci ntal, unplanned, or u ontrolled radioactive release including th preparation of re rts covering evaluation, recommendations, and sposition of corrective action to ,
prevent recurrence and e forwardin of these reports to the Executive Vice President f Shoreh Project; and ,
- q. Review of proposed changes - t approved Decommissioning Plan. l l
6.5.1.7 The SRC shall:
- a. Recomend in writing to t Reside: flanager approval or disapproval l of items considered und Specificai on 6.5.1.6a. through d. and
- n. prior to their imp 1 aentation,
- b. Render determinatio in writing with re rd to whether or not each item consider d under Specification 5.1.6a. through e.
above constitute an unreviewed safety ques on.
- c. Provide writ notification within 24 hours t the Executive Vice Presid t of Shoreham Project of disagreeme t between the SRC and the R ident Manager; however, the Resident M ager shall have responsi lity for resolution of such disagreements ursuant to Specif ation 6.1.1.
RECORDS 6.5.1.8 T SRC shall maintain written minutes of each SRC meeting at, at a mini m, document the results of all SRC activities performed unc. the res nsibility provisions of these Technical Specifications. Copie he shall e provided to the Executive Vice President of Shoreham Project an Inde ndent Review Panel.
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_ cunorum _ m T 1 6-5 _
96L.ETE- PA %. A ISTRATIVE CONTROLS , x 6.5.2\DEPENDENTREVIEWPANEL(IRP) FUNCTION 6.5.2.1 The I shall function to provide independent revie of designated activities in the reas of nuclear safety, radiological con ols, and regulatory complian . In addition, the IRP shall be cog zant of audit activities as describ in Specification 6.5.2.6. The IRP shall report to e LIPA chairman and ultim ely to the LIPA Board of Trustees. COMPOSITION 6.5.2.2 The IRP shall be compose f th RP Chairman and a minimum of four additional IRP members. The chairma d all members of the IRP shall ce appointed by the LIPA Board of Trust from outside organizaticas .:1th demon-strated expertise in the areas of 11 nuclear operations, academia and/or research in nuclear fields, or n ear re lation. The Chairman and all other m iers of the IRP hall have qualifications that meet the education and exp ience requirements Section 4.7 of ANSI /ANS 3.1-1978. The IRP, on a ollective basis, shall technically competent so as to be able to provi oversight in the areas of ministrative controls, nuclear power plant erations, nuclear engineering, ality assurance, radio-logical safety, me anical engineering, and electrical gineering. l HEETING FREQUE Y 6.5.2.3 T IRP shall meet at least once per six months. ; l I l i
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\DfilNISTRATIVE CONTROLS QU 6.5.2. The quorum of the IRP necessary for the performance of the I review nctions of these Technical Specifications shall consist of the Ch rman or his designated alternate and at least two other embers. other The IRP Cha rman shall appoint an alternate chairman from among t RP Chairman members in w iting, in advance of any IRP meetings in which the is not availab e to participate.
REVIEW 6.5.2.5 The IRP sh 1 review:
- a. The safety e luations for (1) changes to uipment or systems and(2) tests experiments completed u er the provision of 10 CFR 50.59 to ve fy that such actions d not consititute an unreviewed safety uestion;
- b. Proposed changes to rocedures, eq pment, or systems which involve an unreviewed afety que ion as defined in 10 CFR 50.59;
- c. Proposed tests or experi nts hich involve an unreviewed safety question as defined in 10 F 50.59;
- d. Proposed changes to Tech ca Specifications of this Possession Only License;
- e. Violations of codes egulations, rders, Technical Specifications, li nse requiremen , or of internal procedures or instructions ving nuclear safe significance;
- f. Significant d iations from normal and xpected performance of station equi ent that affect nuclear sa ty; 9
All REPOP ABLE EVENTS;
- h. All r ognized indications of an unanticipate deficiency in some
- aspe of design or operations of structures, s tems, or c onents that could affect nuclear safety; and
- 1. eports and meeting minutes of the SRC.
AUDITS 6.5 .6 Audits of station activities shall be performed under the c nizance of the IRP. These audits and audit frequencies are as fo ows: '
- a. The conformance of station operation to provisions contained within the Technical Specifications and applicable license conditions at least once per 12 months;
' . ; inca. . :L. ih0REH;E - UNIT 1 - 6-7
C:6LETE PAGG-ADft ISTRATIVE CONTROLS - [ , AUDITS ontinued) f e performance, training and qualifications of the entire st b. a least once per 12 months; sults of actions taken to correct deficiencies oces .on ring in
- c. The that unit e ipment, structures, systems, or method of opera affect clear safety, at least once per year;
- d. The perfor nee of activities required by the Qual y Assurance Program to et the criteria of Appendix B, 10 CF Part 50, at least once pe 24 months;
- e. The fire protect on programatic controls in uding the implementing proc ures, equipment and pro am implementation at least once per 24 nths utilizing either a qualified offsite licensee fire protec fon engineer (s) or n outside independent fire protection consu ant.
- f. Any other area of statio operhtio considered appropriate by the IRP, the President of Sho ham Pr ject or the Executive Vice President ;
of Shorehem Project;
- g. The Radiological Environmen ionitoring Program and the results thereof at least once per mo hs; i
- h. The OFFSITE DOSE CALCUL ON MANUA and implementing procedures at least once per 24 m ths; and
- i. The PROCESS CONTROL ROGRAM and imple. ting procedures for solidification of adioactive wastes at east once per 24 months.
The perforra e of activities required by t Quality Assurance J. Program for ffluent and environmental monito ng at least once per 12 mo s. RECORDS 6.5.2.7 Rec ds of IRP activities shall be prepared, approv - and distributed indicated below:
- a. inutes of each IRP meeting shall be prepared, approved, nd forwarded to the President of Shoreham Project and the Ex utive Vice President of Shoreham Project within 14 days following ach meeting.
- b. Reports of reviews encompassed by Specification 6.5.2.5 shall e prepared, approved, and forwarded to the President of Shorehamwi in Project and the Executive Vice President of Shoreham Project 14 days following completion of the review.
,. - - 6-8
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MbN 2bk ADMINI RATIVE CONTROLS /
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RECORDS (C tinued) Au t reports encompassed by Specification 6.5.2.6 shall t forwarded
- c. dent of to t President of Shoreham Project, Executive Vice Pre Shoreh m Project and to the management positions respo ible for the ,
areas a ited within 30 days after completion of the dit by the auditing rganization. 6.6 REPORTABLE EVENT CTION 6.6.1 The following act s shall be taken for REPORTA E EVENTS:
- a. The Comission sh 11 be notified and a rep t submitted pursuant to the requirement of Section 50.73 to CFR Part 50, and
- b. Each REPORTABLE EVEN shall be review by the SRC, and the <
results of this review hall be sub, ted to the Executive Vice President of Shoreham P ject.
,6 . 7 PROCEDURES AND PROGRAMS 6.7.1 Written procedures shall be est lished, implemented, and maintained covering the activities referenced b ow.
- a. The applicable procedur recomme ed in Appendix A of Regulatory Guide 1.33, Revision 2 February 1 8.
- b. The applicable proc dures required to implement the requirements of HUREG-0737.
- c. Fuel handling erations.
Surveillanc and test activities of safety- lated equipment. d.
- e. Security lan implementation.
- f. Emerg cy Plan implementation.
- g. Fi Protection Program implementation.
- h. ROCESS CONTROL PROGRAM implementation.
1 0FFSITE DOSE CALCULATION MANUAL implementation.
- j. wuality Assurance Program for effluent and environmental monitoring.
anur,tnm - unit i 6-9 Amendment NO. 9_ l I l
DEuEFE PAGE , ADN ISTRATIVE CONTROLS e s e 6.7.2 ch procedure of Specification 6.7.1, and changes thereto, shall reviewed the SRC prior to implementation. The Resident Manager sha approve St ion Administrative Procedures, Security Plan Implementin Procedures d Defueled Emergency Plan Implementing Procedures prio to implementatio Other procedures of Specification 6.7.1 shall be pproved by the appropr te Division Manager or by the Resident Manager or to implementation. ach Division Manager shall be responsible fo a designated set of rocedures. These procedures shall be rey wed periodically as set orth in administrative procedures. 6.7.3 Temporary chang to procedures of Specification .7.1 may be made provided:
- a. The intent of the riginal procedure is t altered;
- b. The change is approv by two members f the unit management staff, at least one o whom holds a enior Fuel Handling Operators Certification on the un affecte and
- c. The change is docurented, vi ed by the SRC, and approved by the Resident Manager within days of implementation.
6.7.4 The following programs shall ee blished, implemented, and maintained:
- a. Radioactive Effluent ontrols progr A program shall b provided confonning ith 10 CFR 50.36a for the control of radi etive effluents and fo aintaining doses to MEMBERS OF TH UBLIC from radioactive ef uents as low as reasonably a ievable. The program (1) sha 1 be contained in the ODCM, (2) all be implemented by operating ocedures, and (3) shall in de remedial actions to be taken whe ver the program limits e exceeded. The program shall include he following eleme s:
- 1) Limitations on the operability of radioactive quid and gaseous monitoring instrumentation including sur illance tests and setpoint determination in accordance wit the methodology in the ODCM.
231iGPIHAh - Uidi 1 6-10 mm.J.mca. :t. O
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)(I AM bb i i ADMINISTRA VE CONTROLS , l
- 2) imitations on the concentrations of radioactive materia l 1 eased in liquid effluents to UNRESTRICTED AREAS c forming to 10 CFR Part 20, Appendix B Table II, C umn l 2, 1
- 3) Monitoingfluentsinaccordancewith10CFR20 sampling, and analysis of rad gaseous f 06 and with the meth ology and paran,eters in the ODCM, i
- 4) Limitations n the annual and quarterly d es or dose commitinent to a HEMBER OF THE PUBLIC fr radioactive materials in 1 quid effluents release . rom each unit to UNRESTRICTED AR. S conforming to App dix I to 10 CFR Part 50,
- 5) Determination of cu 'lative an rojected dose contributions from radioactive eff' ents fo the current calendar quarter and current calendar y r ir accordance with the snethodology and parameteis in the O M t least every 31 days,
- 6) Limitations on the ope i ty and use of the liquid and gaseous effluent tre- nt stems to ensure that the appropriate portion of these ystems are used to reduce releases of radio tivity when he projected doses in a 31-day period w d exceed 2 pe ent of the guidelines for the annual dos or dose corsnitmen conforming to Appendix I to 10 CFR Pa 50,
- 7) Limitati on the dose rate resultin from radiohetive nwteria released in gaseous effluents o areas beyond the SITE - NDARY conforming tc the doses a ociated with 10 CFR Por 0, Appendix B, Table II, Column 1,
- 8) mitations on the annual and quarterly air oses resulting from noble gases released in gaseous effluent from each unit to areas beyond the SITE BOUNDARY conform ig to Appendix 1 to 10 CFR Part 50, l
5"0TI""i l'T : 6-11
b6L,$. t 5 Y ADMINIST IVE CONTROLS , s
- 9) Limitations on the annual and quarterly doses to a MEMBE F E PUBLIC from tritium and all radionuclides in partic ate f with half-lives greater than 8 days in gaseous eff ents released from each unit to areas be3ond t SITE BOUND Y conforming to Appendix I to 10 CFR Part ,
- 10) Limitati s on the annual dose or dose commits t to any MEMBER OF E PUBLIC due to releases of radi ctivity and to radiation f - uranium fuel cycle sources nforming to 40 CFR Part 190.
- b. Radiological Environme tal Monitoring Prog m A program shall be provi to monitor e radiation and rodionuclides in the enviro of the ant. The program shall arovide (1) representat.ive . sure. ts of radioactivity in the lighest potential exposure pat a , and (2) verification of the accuracy of the effluent monito g program and rnodeling of environmental exposure athway . he program shall (1) be contained in the ODCM, 2) c form the guidance of Apper. dix I to 10 CFR Part 50, and 3) nclude ti following:
- 1) Monitoring, sampli , analysis, an eporting of radiation and radionuclide in the environment accordance with the methodology an parameters in the ODCM.
- 2) A Land Use nsus to ensure that changes 'the use of areas at and be nd the SITE B0UNDARY are identi d and that modific- ions to the monitoring program are a e if required by th esults of this census, and
- 3) Pa icipation in a Interlaboratory Comparison Pro to sure that independent checks on the precision and ccuracy of the measurements of radioactive materials in '
environtiental sample matrices are performed as part of e ' quality assurance program for environmental monitoring. i j I l 4"On:"A". - UiuT 1 6-12
l kh CI bb , A NISTRATIVE CONTROLS , 1 x 6.8 ORTING REQUIREMENTS , R0lnINE RTS 6.8.1 In add ion to the applicable reporting requirements of itle 10, Code of Federal egulations, the following reports shall be mitted to the Regional Adm1 strator of the Regional Office of the N unless otherwise noted. ANNUAL REPORTS 6.8.1.1 Annual reports ce ring the activities of he unit as described below for the previous calen r year shall be su itted prior to March 1 of each year. The initial repor was submitted pr r to March 1 of the year that followed initial criticali . 6.8.1.2 Reports required on an ann 1 bac s shall include a tabulation on an annual basis of the number of sta on utility, and other personnel (including contractors) receiving expo res greater an 100 mrems/yr and their associated manrem exposure acc di to work hid ab functions * (e.g., operations and surveillance nspec ion, routine t aintenance, special maintenance (describe mai enance), 'aste proe m ;ng, and fuel handling). The dose assignment to various d functions ma based cn pocket dosimeter, tha noluminescent do meters (TLD)y , orbe estimated film badge measurements. Small e osures totalling le than 20% of the 4 individual total dose need ot be accounted for. the aggregate, at least 80% of the total w ebody dose received from ternal sources should be ussigned to specific ajor work functions. i ANNUAL RADIOLOGICAL VIRONitENTAL OPERATING REPORT 6.8.1.3 The Ann 1 Radiological Environmental Operating Repo covering the operation the unit during the previous celendar year sha 1 be submitted bef e May 1 of ecch year. The report shall include s . aries, interpretat ' ns, and analysis of trends of the results of the Radi ogical Environme al Monitoring Program for the reporting period. The mate al provide hall be consistent with the objectives outlined in (1) the M and(2 Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part .
- " E td;hth: ;;pphmt; th; n;;in:c,t; :f 20.!07 ;f CT" Put 20 :
1 anuun e - vaii A 6-13
7ELG~iE. PA(=E AD 4tSTR ATIVE CONTROLS ANNUAL DIOACTIVE EFFLUENT RELEASE REPORT 6.8.1.4 Th nual Radioactive Effluent Release Recurt covering the operatio of the unit during the previ s 12 months of operation shall be submitted annually, and e time between submiss n of the reports must be no longer than 12 months. T report shall include a summary the quantities of radioactive liquid and gaseous ef ents, and solid waste released from e unit. The material provided shall be: (1) cons' tent with the objectives outlined in t ODCM and PCP; and (2)in conformance h 10 CFR 50.36a and Section IV.B.1 of Ap ndix 1 to 10 CFR Part 50. SPECI AL REPORTS 6.8.2 Special reports shall be s mitted to the Regional ministrator of the Regional Office of the NRC within the time riod specified for e h report. 6.9 RECORD RETENTION 6.9.1 in addition to the applicable record te on requirements of Title 10, Code of Federal Regulations, the following records s be retained for at least the minimum period indicated. 6.9.2 The following records shall be r ained for t least 5 years: ,
+
- a. Records and logs of el handling opera 'ons.
- b. Records and log of principal maintenance -tivities, inspections, repair, and replacement o rincipalitems of equipment lated to nuclear safety.
- c. ALL REPO ABLE EVENTS.
- d. Recor of surveillance activities, inspections, and c ibrations required by the Technical Specifications.
- e. ecords of changes made to the procedures required by ecification 6.7.1. i
- f. Records of radioactive shipments.
- g. Records of sealed source and fission detector leak tests and resu .
i l 6-14 tcc.;c.iT.;r: "?:.10
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M!NE NbE ADMINI TRATIVE CONTROLS < 1
- h. Reco s of annual physical inventory of all sealed source material recor 6.9.3 The fo owing records shall be retained for the duration of e unit License: l '
- a. Records nd drawing changes reflecting station desigt modificat ns made to systems and equipment describ in the ,
Defueled S ety Analysis Report.
- b. Records of ne and irradiated fuel inventory, el transfers, and assembly burnup istories.
- c. Records of radiat n exposure for all ind iduals issued monitoring devices accordance with 10 FR 20.202.
- d. Records of gaseous an liquid radioac ve material released to the environs.
- e. Records of training and qu lific ion for current members of the unit staff.
- f. Records of quality assuranc a ivities required by the Quality Assurance Manual which are et sted in Section 6.9.2.
- g. Records of reviews perf rmed for c nges made to procedures or equipment or reviews tests and e eriments pursuant to 10 CFR 50.59.
- h. Records of meeti s of the SRC and IRP d of meetings of the Review of Operations C iittee and Nuclear Revie Board held by the original lice ee.
- i. Records of nalyses required by the Radiologi 1 Environmental Monitori Program that would permit evaluatio of the accuracy of the alysis at a later date. This should i lude procedures effet ve at specified times and QA records showi that these proc dures were followed.
P cords of reviews performed for changes made to the FSITE DOSE J. LCULATION MANUAL and the PROCESS CONTROL PROGRAM. 6.10 - DIATION PROTECTION PROGRAM 6.1 Procedures for personnel radiation protection shall be prepared sistent with the requirements of 10 CFR Part 20 and shall be approve l c n intained, and adhered to for all operations involving personnel radiat exposure.
"t- o O '^Z " * " ""!' : 6-15 _
[M M N N N , y ADM ISTRATIVE CONTROLS , 1 6.11 H RADIATION AREA , 6.11.1 in lieu of the " control device" or " alarm signal" requi d by paragraph 2 203(c)(2) of 10 CFR Part 20, each high radiation ca in which the intensity )f radiation is greater than 100 mrems/h but 1 s than 1000 ! mrems/h shall barricaded and conspicuously posted as a h h radiation area and entran thereto shall be controlled by requirin issuance of a Radiation Work Pe it (RWP)*. Any individual or group o individuals permitted to enter uch areas shall be provided with or ccompanied by one or more of the fall ing:
- a. A radiation m itoring device which conti uously indicates the radiation dose ate in the area.
- b. A radiation monit ing device which niinuously integrates the radiation dose rate in the area and larms when a preset integrated dcse is r ceived. Entr into such areas with this mcnitoring device may e made af r the dose rate levels in the area have been establis ed and ersonnel have been made knowledgeable of them.
- c. A health physics qualified ndividual (i.e., qualified in radieticn protection proc u s) with a radiation dose rate monitoring device, who i res noible for providing positive control over the activ ies wit in the area and shall perform periudic radiation su eillance - the frequency specifiec by the Health Physics Engi er in the RW 6.11.2 In aadition to the equirements of Spe fication 6.11.1 areas accessible to personnel w h radiation level:; su h that a major portion of i the body could receive i 1 hour a dose greater t n 1000 mrems shc11 be provided with locked dc rs to prevent unauthorized ntry, and the keys '
shall be raintained u er the administrative control f the Watch Supervisor on duty a d/or the Health Physics Engineer. Doors shall remain locked except duri periods of access by personnel un r an approved RWP i which shall speci the dose rate levels in the imediat work area and the maximum allowab stay time for individuals in that area. For individual l areas accessib to personnel with radiation levels such th t a major l portion of th body could receive in 1 hour a dose in excess f 1000 mrems** tha are located within large areas, such as the cont nrent ,
- Heal physics personnel or personnel escorted by health physics l per nnel shall be exempt from the RWP issuance requirement durin the l pe ormance of their assigned radiation protection duties, provided they I e otherwise following plant radiation protection procedures for en; nto high radiation areas.
** Measurement made at 18 inches from source of radioactivity.
- ELEA -vet- 6-16 l l
DSI CW. WW ADMIN TRATIVE CONTROLS n be , where no e closure exists for purposes of locking, and no enclosure. all be ! reasonably nstructed around the individual areas, then that area l vated as roped off, co picuously posted, and a flashing light shall be ac WP, In lieu of the stay time specification of th l a warning devi direct or remote (such as use of clos circuit TV
. l continuous surve lance, '
cameras) may be ma e by personnel qualified in radiation prorthin ction the area. ] procedures to provi exposure control over the activities 6.12 PROCESS CONTROL OGRAM (PCP) Changes to the PCP:
- a. Shall be documente nd records of revi s performed shall be retained as required Specification .9.3.j. This documentation shall contain:
- 1) Sufficient informati toosuevaluations ort the change together with justifying the the appropriate analys change (s) and
- 2) A determination that e c. nge will maintain the overall confomance of the s idifie waste product to existing requirements of Fe ral, State or other applicable regulations.
- b. Shall become effec ve after review and cceptance by the SRC and the approval of t Resident Manager.
6.13 0FFSITE DOSE CALCU TION MANUAL (ODCM) Changes to the ODCM:
- a. Shall b documented and records of reviews perform shall be retain d as required by Specification 6.9.3.j. This ocumentation shal contain:
Sufficient information to support the change togeth with
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1 the appropriate analyses or evaluations justifying th change (s) and _Sugqru w netT 3 - 6-17 , _m ,, g
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i AD ISTRATIVE CONTROLS (Continued) A determination that the change will maintain level of radioactive filuent control required by 10 CFR 20.10 0 CFR Part 190,10 , C 50.36a, and Appendix 1 to 10 CF rt 50 and not adversely impac e accuracy or reliability of uent, dose, or setpoint calculatio
- b. Shall become effective r rev' and acceptance by SRC and the approval of the Resident Manager. .
Shall be submitted to e Commissi in the form of.a complete, legible c. copy of the entire CM as a part of, oncurrent with, the Annual Radioactive Ef ent Release Reoort for the riod of the report in which any. change to ODCM was made. Each change all be identified by , l markin n the margin of the affected pages, clea indicating the area of ' : the e that was changed, and shallindicate the dat .g., month / year) change was implemented. t s-18 - 4- :- =
-Sace.a ce =3
APPENDIX B TO FACILITY OPERATING LICENSE NO. HOREHAM NUCLEAR POWER STATION, UN 1 LONG ISUtHD LIGHTING COMP Y DOCKE! NO. 50-3 ENVIR ' MENTAL PROT TION PLAN (NON DI OGICAL) SH0REHNi NUC AR POWER STATION , UNIT ENVI NMENTAL PRO TION PLAN (NON-RADIOLOGICAL June 14, 1991 f
dE bb TABLE OF CONTENTS Section Page 1.0 OBJECTIVES THE ENVIRONMENTAL PROTECTION PLAN...... ........ 1-1 2.0 ENVIRONMENTAL OTECTION ISSUES................... ............. 2-1 2.1 Aquatic Issues.... ........................... ................ 2-1 2.2 Terrestrial Issues... ..................... ................... 2-2 3.0 CONSISTENCY REQUIREMENTS.. ............ ....................... 3-1 3.1 Facility Design and Operation ..... .......................... 3-1 3.2 Reporting Related to the SPDES P .1t.......................... 3-2 3.3 Changes Required for Complian wit Other Envirorr, ental Regulations. ........ ........................ 3-3 4.0 ENVIRONMENTAL CONDITION .................. .................... 4-1 4.1 Unusual or Important nvironmental Events.... ................. 4-1 4.2 Environmental Ho oring and Other Requirements. .................................. ............ 4-1 5.0 ADMINISTRA VE PROCEDURES 5.1 Review d Audit.......................................... ... 5-1 5.2 Reco s Retention............................................ 5-1 5.3 C nges in Environmental Protection Plan...................... 5-2 5.4 F a cility Reporting Requi reme nts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
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-{ 1. OBJECTIVES OF THE ENVIRONMENTAL PROTECTION PLAN F
The Envi ental Protection Plan (EPP) is to provide for prote on of nonradiologi 1 environmental values during the defueled con tion of.the : nuclear facility The principal objectives of the EPP ar as follows: ! (1) Verify that facil is maintained in an env onmentally acceptable manner, as establish by the Final Envir ental Statement-Operating License Stage (FES-OL) a other NRC vironmental impact assessments. l t (2) Coordinate NRC requirements an maintain consistency with other Federal, State and local r uirem ts for environmental protection. ; (3) Keep NRC informed o the environmental e ects of facility maintained in the defueled to tion and of actions taken o control those effects. Environmental oncerns identified in the FES-OL which r ate to water , quality ma ers are regulated by way of the New York State ollutant l Dischar e Elimination System (SPDES) permit, issued to licens . P
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2.0 ENVIRON!4 ENTAL PROTECTION ISSUES In the FE OL dated October 1977, the staff considered the environm6 al impacts asso ted with the operation of the Shoreham Nuclear Pow Station, Unit 1. Certain environmental issues were identified hich required study or 1 ense conditions to resolve environment concerns and to assure adequate pro ction of the environment. 2.1 Acuatic Issues Specific aquatic issues raised by t e staff n the FES-OL were: (1) The need for discharge related uat e monitoring programs to confirm that the station's cooling w er system ith its offshore submerged diffuser performs as pred ted and is prot tive of indigenous biota of Long Island Sound, om 6 thermal and chem al discharge standpoint (FES-OL sumary an conclusions and Sections 5.4 nd6.3). (2) The need for ntake-related studies to document levels f intake entrainme and impingement, to determine survival of ent ined ichthy lantkton, and measure the effectiveness of the fish turn sy em in protecting impinged fish (FES-OL sumhry and conclusic s and ections 5.4, 6.3 and 10.4). l l 2-1 ! 1 i
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'(3) Th need for monitoring existing wells on the Shoreham site and he Shor am-West site to detect effects of plant operation on b h water level a water quality (FES-OL Section 6.3.3).
Issues (1)and(2) re addressed by the effluent limitat ns, monitoring requirements and othe conditions contained in the SP S permit issued by the New York State Depar ent of Environmental con rvation(NYSDEC). The NRC will rely on the NYSDEC or regulation of m ters involving water quality and aquatic biota. NR requirements ith regard to issue (3) are no longer applicable in the DEFUEL D MODE 2.2 Terrestrial Issues The specific terrestrial issu raised by the taff in the FES-OL are: (1) The need to protec Wading River Marsh from de sition of sand and other materials ransported from the Shoreham sit (FES-OL Sumary and , Conclusions d Sections 4.2, 5.2, 6.2.4 and 6.3.6). (2) The ne formonitoringandmitigatingbeacherosion(FES-. Sumary and onclusions and Sections 4.2, 5.2, 6.2.4 and 6.3.6). , 2-2
M6kbN'N (3) The eedforcontrolleduseofherbicides(FES-OLSection5.4.1). i (4) The need or monitoring the mortality of migratory birds res ing from collis n with the meteorological tower and plant st ctures (FES-OLSecti 6.2.4 and 6.3.6). NRC requirements with r ard to issues (1) through (3) re specified in Section 4.2 of this EPP; i ue (4) is covered by Se ion 4.1 of this EPP.
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o M tE.W % & 3.0 ONSISTENCY REQUIREMENTS 4 3.1 Facil ty Design and Operation The licensee ma make changes in facility design or operati or perform tests or experimen affecting the environment provided s ch activities do not involve an unrevi ed environmental question, and not involve a change in the EPP.* Cha es in facility design or eration or performance tests or experiments which o not significantly fect the environment or t that are covered by the SPDES ermit are not s ject to the requirements of this EPP. Activities governed b Section 3 are not subject to the requirements of this section. Before engaging in additional cons ucti , or activities which may significantly affect the environment, the lic see shall repare and record an environmental evaluation of each such activ' y. Activities re excluded from this requirement if all measurable nonradio gical effects are to ined to the onsite areas previously disturbed du ng site preparation and fa ility construction. When the evaluation indic es that such activity involves a unreviewed environmental , l question, the lice see shall provide a written evaluatio of such activity and obtain prior NR approval. When such activity involves a c nge in the EPP, such activit and change to the EPP may be implemented only in accordance with i an appropr ate license amendment as set forth in Section 5.3 of is EPP. l 1
*This rovision does not relieve the licensee of the requirements of CFR 50 9.
3-1 j l
WW Y A propose hange, test or experiment shall be deemed to involve an unreviewed e ironmental question if it concerns (1) a matter which y result in a sig 'ficant increase in any adverse environmental imp t previously evaluat in the FES-OL, environmental impact appra als, or in any decisions of the omic Safety and Licensing Board; or -) a significant change in ef uents or design power level; o (3) a matter not previously reviewed and eva ated in the documents sp ified in (1) of this subsection, which may have a s nificant adverse e ironmental impact. The licensee shall maintain recor of changes ' facility design or operation and of tests and experimen carri d out pursuant to this subsection. These records shall inclu ritten evaluations which provide i bases for the determination that the . an , test, or experiment does not involve an unreviewed environmenta question r constitute a decrease in the effectiveness of the EPP to eet the object es specified in Section 1.0. 3.2 Reporting Related o the SPDES Permit Changes to, or r ewals of the SPDES Permit shall be reported o the NRC within 30 day following the date the approved change or renewal 's received. f a permit or certification, in part or in its entirety, is appeal and stayed, the NRC shall be notified within 30 days followin the day e stay is granted. 3-2
WI FW & 1 The licens e shall notify the NRC of changes to the effective SPDES pe t proposed by e licensee by providing the NRC with a copy of the pro sed change at the s time it is submitted to the permitting agency. The licensee shall pro ide the NRC a copy of the application for r ewal of the SPDES permit at the me time the application is submitted t the . l permitting agency. 3.3 Changes Required for Co, liance with Other Env onmental Regulations 5 Changes in f acility design or oper tion and pe ormance of tests or experiments which are required to ac ' eve c apliance with other Federal, , State and local envircrmental regulatio are not subject to the requirements of Section 3.1. i l i
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3-3 ) I
l l dN N g 4.0 E IRONMENTAL CONDITIONS 4.1 Unusua or Important Environmental Events Any occurrence o an unusual or important event that indic. es or could result in significa environmental impact causally rel ed f.o maintaining the facility shall be ecorded and promptly reported o the NRC within 24 hours followed by a writ n report per subsection .4.1. The following are examples: excessive bird action events, ons e plant or animal disease ! outbreaks, mortality or unusu occurrence o any species protected by the ! Endangered Species Act of 1973, sh kill , increase in nuisance organisms or conditions, and unanticipated o em gency discharge of waste water or chemical substances. No routine monitoring programs re require to implement this condition. 4.2 Environmental Mcnito ing and Other Reauire, nts 4.2.1 Protection o Wading River Marsh l The applicant all protect Wading River Marsh, including hose portions owned by th Applicant, from deposition of sand and other ma rials ! transpor d from the facility site. Ultimate control shall be rimarily by : groun cover, other vegetation and administrative action. Relian may el be upon snow fencing and similar physical barriers. There shal be no outine reporting requirement associated with this condition. 4-1 ,
J ~ l W LE.T E. T A M 4.2.2 Beach Erosion The applica t shall monitor the accumulation and/or erosion of beac sand and gravel in he vicinity of the facility site. Any beach mater al eroded from east of the pplicant's jetties shall be replaced with ac mulated sand, if any, from ding River Creek, from the 1000-foot-1 g intake channel, from between he jetties, and from the east and est sides of the jetties. There shall be o routine reporting requirerr nt associated with this cor.dition. 4.2.3 fleintenance of Transmissi Line Corri rs The use of herbicides within the Shore a Nuclear Power Station transmission line corridors shall con r to the approved use of selected herbicides as registered by the Env ronment 1 Protection Agency and approved by State authorities an applied as rected by said authorities. Records shall be maintaine in the appropriate divi ion office concerning herbicide use. Such rec ds shall include the follow information: connercial and chemic naraes of materials used; concent tion of active material in formul ions diluted for field use; diluting su tances other than water; rate of application; method and frequency of app cation; , location; and ' ate of application. Such records shall be mainta d for a period of years in conformance with NYS Department of Environment 1 Conserve ion requirements and be made readily available to the NRC up reque . There shall be no routine reporting requirement associated wit th cordition. 4-2 r _ ___ _ )
l [IT MO 5.0 A INISTRATIVE PROCEDURES I 1 l 5.1 Review d Audit 1 The licensee shall rovide for review and audit of compliance th EPP. The audits shall be ducted independently of the individ or groups responsible for perform the specific activity. A des iption of the organizational structure u 'lized to achieve the inde ndent review and audit function and results of he audit activities shall be maintained and made available for inspection. 5.2 Records Retention Records and logs relative to the en ronmen 1 aspects of maintaining the facility shall be made and retai d in a manne convenient for review and inspection. These records an logs shall be made vailable to NRC on request. Records of modificat' ns to facility structures, systems d components determined to hav the potential to significantly affect the ontinued protection of e environment shall be retained for the life o the facility. 1 other records, data and logs related to this EPP s 11 be retained or five years or, where applicable, in accordance with the requi ments of other agencies. 5-1 I
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- Dd i 5 % drb 5.3 C nges in Shoreham Environmental Protection Plan Request for hange in the EPP shall include an assessment of the environmental pact o theproposedchangeandsupportingjustiication.
Implementation o- he; es in the EPP shall not commence prior ,o NRC approval of the prop sed changes in the form of a license endment incorporating the appr riate revision to the EPP. t 5.4 Plant Reporting Require ents 5.4.1 Nonroutine Reports A written report shall be submitted t he NRC within 30 days.of occurrence of a nonroutine event. The report all ) describe, analyze, and evaluate the event, including ex nt and mag itude of the impact and facility operating characteri ics, (b) describ the probable cause of the event, (c) indicate the at on taken to correct t reported event, (d) indicate the corrective ction taken to preclude rep ition of the event and to prevent simil occurrences involving similar to onents or systems, and (e) indicate e agencies notified and their prelimin y responses. Events repor ble under this subsection which also require repo ts to other Federal, ate or local agencies shall be reported in ac.ordance th those report g requirements in lieu of the requirements of this subsectio The NRC hall be provided a copy of such report at the same time it is mitted to the other agency. 5-2}}