ML19308B204
| ML19308B204 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/13/1978 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19308B202 | List: |
| References | |
| NUDOCS 7912160081 | |
| Download: ML19308B204 (24) | |
Text
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o UNITED STATES y
s NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 205$5 Q"6//
DUKE POWER COMPANY DOCKET NO. 50-269 OCONEE NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE I
Amendment No. 57 License No. OPR-38 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) cated March 1, 1977, as supplemented December 15, 1977, complies with the standards and requirements of the Atomic Energy Act of
'954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act., and the rules and regulations of the Cocrnission:
C.
There is reasonable assurance (i) that the activities authorized by this amendment 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; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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Accordingly, the license is amended by enanges to the Technical Specifications as indicated in the attachment to tnis license amend ent and paragraph 3.5 of Facility License No. OCR-38 is hereby amended to read as follows:
3.5 Technical Soecifications The Tecnnical 5:ecifications contained in ::cendices A and 3, as revised through Amendmer.: No. 57, are hereby incor: orated in tne license. The licensee shall Ocerate one facilicy in accordance witn tne Technical 5:ecifications.
3.
This license amendment is effective within 20 days of the date of issuance.
FOR THE N"S EAR REGULATORY COMMISSION
'./javaan A. 3chwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to tne Technical Specifications Cate of Issuance:
February 13, 1978 4
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p as4 9*o UNITED STATES J"
- ,f NUCLEAR REGULATORY COMMISSION a
WASHING TON, 0. C. 20555 t
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jf DUKE POWER COMPANY DOCKET NO. 50-270 OCONEE NUCLEAR STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. DPR-47 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated March 1,1977, as supplemented December 15, 1977, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), a a the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission:
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conductec in compliance witn the Commission's regulations; D.
The issuance of this amendment will not be inimical to the conmon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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2 2.
A:::rdingly, the license is amended by changes to the Technical Specifications as indicated in the attacnment to this license amer:: eat and :aragra:k-3.S of Fa:ility License No. OPR-47 is he et a.ende tc read as follows:
- 3. 3 Tecnnical 5:ecifications The Techni:31 S ecifi:ations contained in A::encices A and 3, as revised tnrougn A.mendment Nc. 57, are hereby in:ce: orated in the license.
The licenses sha71 c:e-ate tne fa:ility in accordance witn :ne Te:hnical 5:eci'ications.
This license a..endment is effective within 20 days of the date of 3.
T issuance.
FOR THE NUPLEAR REGULATORY COMMISSION i
1 f(fQ *c'lb W l(,
s
' A. Schwencer, Chief i
Ocerating Reactors Branch 41 Division of Operating Reactors I
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Attachment:
Changes to the Technical Specifications Cate of Issuance: February 13, 1978 e
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WASHINGTON. O. C. 20555
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DUKE POWER COMPANY DOCKET NO. 50-287 OCONEE NUCLEAR STATION, UNIT NO. 3 AMENCHENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. DPR-55 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duke Power Company (the licensee) dated March 1, 1977, as supplemented December 15, 1977, complies with the standards and recuirements 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 operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission:
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health r.d safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the ccamon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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2-2.
Accordingly, te.e license is amended by changes to the Technical Speci'ficatiens as indicated in the attacnment to this license amer.d?ent and paragraph 3.3 of Facility License No. Opa-55 is he eby a.? ended : *ead as follCws:
3.8 Tecnnical Sceci#ications The Tecnnical 5:e:ifications contained in A;;endices A and 3, as revised througr A,mendment No.
54, are he eby incorcorated in tne license. The licensee shall coerate the facility in acc0edance wi*n the Technical 5:ecifications.
3.
This license amendment is effective within 20 days of the date of issuance.
FOR THE NUCLEAF REGULATORY CCMMISSION lA.Schwencer, Chief
,cWadAV Operating Reactors Branch #1 Division of Operating Reactors Attacnment:
Changes to the Technical Specificctions Date of Issuance:
February 13, 1978 4
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 57 TO CPR-38 AMENDMENT N0. 57 TO DPR-47 o
AMENDMENT NO. 54 TO DPR-55 DOCKET NOS. 50-269, 50-270, 50-287 Revise Appendix A as follows:
Remove the following pages and replace with identically numbered pages.
iii iv v
6.1-1 6.1-2 6.1-5 6.1-6 6.1-7 6.1-8 6.4-1 f
Add the following new pages:
3.17-1 3.17-2 3.17-3 3.17-4 3.17-5 4.19-1 4.19-2
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Sectien F0"2 3.4 STE/21 A1:D POWER CO:./ERSIO:' SYSTO 3.4-1 3.5 INSTRU1!C.~ RATION SYSTC!S 3.5-1 3.5.1 Coerational s rce. T.s:ru-entarien 3.5-1 3.5.2 Control Red Crcua ar.3 Pet.er Distributien Limits 3.5.6
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3.5-25 3.5.3 Ingineered Fifttv Features Proceerf ve Svr. en Actuation Set,oints 3.5-27 3.5.4 Intere Instru-entetic, 3.6 REACTOR SUILDI::G 3.6-1 3.7 AUXILIARY ELECTF.ICAL SYSTDIS
.3.7-J 3.8 TUEL LOAD!::G A:D RE7UELI::
3.S-1 3.9
. RELEASE OF LIQ'.*1D 1%DICACTIVE WASTE 3.
1 3.10
' RELEASE OF GASECUS MDICACTIVE WASTE 3.10-1 3.11 2 AXEC l'OL'ER RESTRICTIONS 3.11-1 1
3.12 REACTOR EUILDI::0 001.AF. CRASE A 0 AUXILIARY !!OIST 3.12 1 3.23 SECO::!r.RY SYSTC: ACI1VITY 3.13-3 3.14 SHOCK SUPPRESSORS (SNUSSERS) 3.14-1 3.15 PENETRATION ROCM VENTILATION SYSTEMS 3.15-1 3.16 HYCROGEN PURGE SYSTEM l
3.17 FIRE PROTECTION AND J 7CTION SYSTEMS 3.17-1 4
. SUnvt111... :ct M'.rci:o: n: :Ts 41 4.0 SURVEILLASCE STA::DA snS 4.13 1
4.1 OPEMT70!:AL SAFETY RL'/IE-4.1-1, 4.2 REACTOR CC01.*.5T SYS!D1 SURVEILLA:4:E 4.2-1 4.3 TESTING FOLLOWING 0?I:I::0 0F SYSTD1 4.3-1 1
i 4.4 REACTOR 3UILDING 4.4-1 iii Amendments 57, 57 1 51
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Pane Section 4.4-1 4. 4.1.
ContnIn-ent Lerkere Tests f 4-6 4.4.2 Structural Ir.tecrity Hvdroen?urceS.stek 4.4-10 4.4.3 4.5 C4ERGENCY CORE CCOLINO SYSTD:S AND REACTOR 3UILDING 4.5-1 COOLING CYSTE:S PT.RICDIC TESTI ;G 4.5.1 Emernency Core Coeline Svstems 4.5-1 4.5.2 Reactor Building Cooling Svstems
- 4. 5-6 4.5.3 Penetration Room' ventilation Svstem 4.5-10 Lov Pressure In e:: ton System teakage 4.5-12 4.5.4 d
4.6 EMERGENCY POWER SYSTEM PERICDIC TESTING 4.6-1 4.7 REACTOR CONTROL RCD SYSTEM TESTS 4.7-1 4.7.1 Control Rod Drive Svstes ?unctional Tests 4.7-1 4.7.2 Control Red Progra Verification.
4.7-2 4.8 MAIN STEM 4 STOP VALVES 4.8-1 4.9 EMERGENCY FEEDWATER PUMP PERIODIC TESTING 4.9-1 i
4.10 REACTIVITY ANCMALIES 4.10-1 4.11 ENVIR0hM. ENTAL SL*RVEILLANCE 4.11 I 4.12 CONTROL ROOM PILTERING SYSTEM 4,12-1 4.13 FUEL SURVEILLANCE 4.13-1 1
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4.14 REACTOR BU!LDING PURGE FILTERING SYSTEM 4.14-1 4.15 IODINE RADIATION MONITORING TILTERS 4.15-1 4.16 RADI0 ACTIVE MATERIALS SOURCES 4.16-1 4.18 HYDRAULIC SHOCK SUPPRESSORS,(SNUBBERS) 4. 1 8 1-4.19 FIRE PROTECTION AND DETECTION SYSTEM 4,1g_1 iv Amendments 57, 57 & 54
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Section 5 1-1 DESIGN FEATURES 3
5.1-1 5.1 SITE 3.2-1 5.2 CONTAI!OiEST 5.3-1 5.3 REACTOR 5.4' NEW AND SPENT FUEL STORAGE FACILITIES 5.4-1 6.1-1 6-ADMINISTRATIVE CONTROLS 6.1-1 6.1 ORGANIZATION, REVIE*4, AND AUDIT 6.1-1 6.1.1 Oreanization 6.1.2 Review and Audit 6.1-2 6.2 ACTION TO BE TN<IN IN THE EVENT OF AN INCIDENT 6.2-1 REPORTABLE TO THE CCMMISSION
- 6. 3, ACTION TO BE TAKEN I!: THE LTE :T A SAFETY LD!IT IS EXCEDD 6.3-1 6.4 STATION OPE *.ATING PROCEDCES 6.4-1 1
6.5-1
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6.5 STATION OPERATI:: RECO.VS 6.6 STATION REPCRTI::G REQ';IRC ENIS 6.6-1 6.6.1 Routine Reeerts 6.6-1 6.6.2 Non-Rou tne Reeeres 6.6'6 6.6.3 Seceial Recor:=,
6.6-9 6.7 RADIOLOOICAL CC:TROLS 6.7-1 v
kendments 57, 57 & 54
3.17 FIRE PROTECTION AND TECTICS SYSTEMS Aeolicab il,i:v.
-a This specification applies to the operability of fire protection and detection sys: ems which protect systems and equipmen recuired for safe shutdown.
Cbjective To assure the operzbility of fire pro:ection and detection sy stem Specification 3.17.1 The minimun fire detection instrumentation for each fire detection
- ene shown in Table 3.17-1 shall be operable.
When this specification is determined not to be met, appropriate action shall be taken consisting of one or more of the following:
Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, a fire watch patrol shall be established to inspec:
1.
an accessible :ene with the inoperable instrumentation at leas t once per hour.
The inoperable instrumentation'shall be restored to operable 2.
status within la days or a report shall be submit:ed to the Commission within the nex: 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the instrumentation to operable status.
3.17.2 Two high pressure service water pumps with a capacity of 6000 gpm each and with automatic initiation logic shall be operable and aligned to the high pressure fire header. When this specification is determined no: to be met, appropriate action shall be taken consisting of the following:
1.
The inoperable equipment shall be restored c operable status within 7 days or a report shall be submitted to the Commission within the next 30 days outlining the plans and procedures to be used :o provide for the loss of redundancy in this system.
2.
With no Fire S'uppression Water System operable, in lieu of the-above, the following action shall be taken.
a)
Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a backup Fire Suppression Water System shall be established, If a backup Fire Suppression Na:er System cannot be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, place the reactor in Hot Standby within the nex: twelve (12) hours and in cold shutdown within the following forty-eight (48) hours.
b) Within :4 hours the Ccomission shall be no:ified by telephone, and in writing no later than the first working day following the
- event, c)
Within la days of the event, a report shall be submitted to the Commissior ot.: lining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status.
1 3.17-1 Amendments 57, 57 & 54 k_
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3.17.3 The sprinkler sys:ess in safe:y rela:ed areas lis:ed in Table 3.17-1 shall be Operable.
If a sys:es is de: ermined to be inoperable, the
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f oll:ving :: ree:ive ac:i:n shall be taken.
1.
.; een:inueus fire va::h vi:h backu; fire su;;;essi:n equi;nen:
shall be es:ab'ished in :he area vi:hin 1 h ur.
2.
The sprinkler sys:em shall be res:::ed :s :perable s:a:us within la days :: a repor: shall be subni::ed :o :he Cec =is-si:n vi:hin the nex: 30 days cu: lining :he :ause of inoper-abili:y and :he plans f:: rest: ring :ne sys:e= :o operable s:a:us.
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3.17.4 The fire hose sca:icas listed in Table 3.1,7-1 shall be operable or additional equivalen: capaci:7 hoses shall be ;;ovided a: an c; era' ole hose station vi:hin one heur such tha: :he addi:icnal hoses can be readily conne::ed :o the c;erable s:1:1:a and ex: ended in:o the un;;c:ee:ed area if :he need arises.
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3.17.5 When a penetra: ion fire barrier crotecting a safe:y related acer.
is determined :o be non-functional, the area shall be pro:ec:cd by operable fire detection instrumenta:*on and wi:hin one hour a fire wa:ch patrol shall be established to inspec: the area a: least
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once per hour.
If :he the fire de:ec: ion ins:rumen:a:icn in :he area is inoperable, a continuous fire watch shall be es:ablished on at leas: one side of the affected pene:ra: ton within ene hour.
...s-a Amendments 57, 57 3 54
TA3LZ 3.17-1
'l Fire Detection Instrumentation A.
DETECTORS PROVIDED/0PEROLE ELE 7 UNIT EQUIPMEN!/LCCAT!ON PROTECTED 773+0 1-2 Motor Centrol Centers 3/2 3
Motor Centrcl Centers 2/1 1/1 775+0 1
Emer FW Pump 1/1 2
Emer FW Pump 3
Emer FW Pu=p 1/1 796+6 1
Reactor 31dg Penetrations 4/4 4/4 RC?'s
'3/2 R3CU 2
Same as Unit 1 3
Sa=a as Unit 1 12/6 1-2 Equipment Room 5/3 3
Equip =ent Roem
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1 Lead Centers, Switchgear 11/6 2
Same as Unit 1 3
Load Centers, Switchgear 9/4 1-2 Switchgear, Transf or:er 4/2 3/2 3
Switchgear 809+3 1
3attery Room 2/1 3/2
, Motor Centrol Centers 1-2 Cable Spread Rcca 8/4
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2/1 2
3attery Room Motor Centrol Centers 3/2 2/1 3
Battery Room Motor Centrol Centers 3/2 3
Cable Spread Room 6/3 1
822+0 1-2 Control Recs 4/2
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1 Penetration Room 4/4 1
Cable shaf t 1/1 l
Amendments 57, 57 3 5J 3.11-3
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TA3LE3.17-1(C0Kf+}
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DETECTORS ELZ7 UNIT EQUIFrr.NT/ LOCATION PROTECTED PROVIDED/0PERA3LE
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4/4 2
Penetration Room 2
cable Shs'.c 2/1 3/2 3
Contri. Roem 4/4 3
Penetration Room 1/1 3
Cable Shaft 3.
Sprinkler Systems Emergency FDWTR Pump Units 1, 2 and 3
" Transformers CT-1
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CT-2 CT-3 CT-4 s
CT-5
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C.
Fire Hose Stations ELE 7 771+0 HOSE STATION No.
Hose Station (Turbine Building)
AX-1 TB I-B-19 TB 3-D-28 TB 1-D-28 TB 3-D-43 AX-2 TB 1-D-39 TB 3-F-42 TB 1-D-45 TB 3-J-23 AX-3 TB 1-D-53 TB 3-J-28 TB l-F-43 TB 3-J-32 AX-4 TB 1-J-23 TB 3-J-40 TB 1-J-28 TB 3-J-47
- AK-5 TB 1-J-32 TB 3-M-24 TB 1-J-43 TB 3-M-29 ELIV 733+9 TB 1-J-47 TB 3-M-30 '
TB 1-M-24 TB 3-H-39 AX-6 TB 1-M-29 TB 3-M-43 TB 1-M-31 AX-7 TB 1-M-43 TB 5-M-24 TB 5-M-31 AX-8 TB 5-M-42 AK-9 AX-10
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Ak-11 Amendments 57, 57 & 54 3.17-4 i
BASES Operability of the fire detection instrumentation ensures that adequate warning capability is available for the prompt detection of fires.
This capability is required in order to detect and locate fires in their early stages.
Prompt de:ection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program.
In the event that a portien of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to operability.
The operability of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires occurring in aaf portion of the facility where safety related equipment is located.
The fire suppression system consists of the water system, spray and/or sprinklers, and fire hose stations.'
The collective capabili;y of the fire suppression systems is adequate to minimi:e potential damage
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to safety related equipment and is a major element in the facility fire protection program.
In the event that portions of the fire suppression systems are inoperable, alternate backup fire fighting equipment is required to be made available in the affected areas until the inoperable equipment is restored to service.
In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant.
The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued operation of the nuclear plant.
The functional integrity of the penetration fire,.rriers ensures that fires will be confined or adequately retarded from spreading to adjacent portions of the facility. Thii design feature minimi:es the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment.
The penetration fire barriers are a passive element in the facility fire protection program and are subj ect to periodic inspections.
During perleds of time when :he barriers are not functional, a fire wa:cn patrol will be required to inspect the area a: least once per hour and fire detec:lon ins:rumen:ation will be operable'in the area.
If fire de:ection instrumentation is not operable, a continuous fire watch is required to b'e maintained in the vicinity of :he affected barrier un:ll the barrier is re-stored to func:ional s:a:us.
3.17 5 Amendments 57, 57 & 51
-i 4.19 F(RE'200TECTICN AND DETEC~ ION Sv57~.9 Acclicabill:v A plies :c the fire Orotection and Oe:ection systems wh*ch pectect systens and ecu;pment required ?ce safe shut cwn.
Obicc:ive To verify the operability of fire protection and de:e::icn sys: ems.
Soecifica:icns 4.19.1 The High Pressure Fire Protection System componen:s shall _be tested as follcws:
Frecuency 1:em (a)
High pressure service wa:er pump Monthly functional tes:
(b)
System functional test Every 18 ncnths (c)
High pressure service wa:er pump Annually cacacity :es: :o verify ficw of 3000 gpm (d)
System Flew Test in Accordance with Every 3 years Chapter 5, See: ion 11 of.the Fire Protection Handbook,14th Edi tion, NFPA (e)
Alignmen: of fire protection valves Monthly (f)
Sprinkler syste.ns in safety related areas 1.
System functicnal :es:
Annually 2.
Insoecticn of spray headers Annually 3
Inspecticn of spray or:le Annually (g)
Fire hose stations 1.
Visual inspec: ion Monthly 2.
Maintenance inesection Annually 3
Partial opening of fire hose Every 3 years station valve 4.
Hose Hydros:a:ic :es: a: leas:
Every 3 years 50 psig grea:er than :he maximum pressure a: :he station 4.19-1 Amendt.en ts 57, 57 & 54
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s 4.19.2 The fire detection system shall be tested for operabilley as follows:
Item Frecuency 4
(a) Operability of detectors Semi-Annually (b)
Operability of annunciators Semi-Annually The testing. interval for detectors which are inaccessible due to power operation may be extended until such time as the detectors become accessible for a minimum of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
The testing interval shall not extend past a refueling. outage.
4.19.3 Penetration fire barriers protecting safety-related areas shall be verified functional by visual inspection at least once per 18 months and prior to declaring a penetration fire barrier functional following repairs or maintenance.
9 4.19-2
- Amendments 57, 57 & 54 o
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6.0 AOMINISTRATIVE CONTCLS
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6.1 ORCAN!1A!!CN, REVIIV, AND AU3!!
6.1.1
~ organi:a:ica 6.1.1.1 The s:stion Manager sha'l be responsible fer everall facili:y opera:!cn and shall delegste in wri:ing :he sue:cssion to :his responsibliity during his absenec.
6.1.1.2 in all matects pertsining to actual opers:io. and sain:enance and to these Technical Specifics:icns, :he ses:ica Manager snall report to and be directly responsible :c :he Vice President, Steam ? reduction, through the Manager, N2 clear Freduction.
The organiza:ica is shown in Figure 6.1-2.
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6.1.1.3 The station organi:atien for Opera:icns, Te:hnical Services and Maintenan:c shall be fune:ionally as shewn in Tigure 6.1-1.
Mini =um opera:ing shift requiremen:s are V;ecified in Table 6.1-1.
6.1.1.4 Incorpora:ed in the staff of the's:a:ica shall be personnel meeting the minimum requiremen:s encompassing the training snt. experier.:e described in See: ion 4 of :he ANSI N18.1-1971, "Salec:icn and Training of Nuclear ?cwer Plan: Personnel."
. 6.1.1.5 Rettsining and replacement of s: scion personnel shall be in
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sceurdance with See:icn. 5.5 of the ANSI N! 8.1-1971, "Selwetion and Trsining cf Nuclea Powur Plant ? cts,ennel."
A training program for the fire brigade shall meet er exceed 6*1.1*6 the requirements of Section 27 of the NFPA Code-1975, except that training sessions may be held quarterly.
6.1.2 Technical Review and Centrol 6.1.2.1 Ac:ivi:ies Precedures required by Technical Specifica:ica 6.1 snd c:her precedures a.
which affe : station nuclear saf e:y, and changes (c:her than editorial or
- ypogVaphi:al changes) :hore:c, shall be prepared by'a' qualified individual /
cegani:acion.
Each su:S procedur'e', or procedure chsag~e, shall be reviewed by an individual / group c:her :han the individual / group whien prepared :he precedure, or procedure change, bu: who say be from the same organi:stion as :ne individual / group which prepared the precedure, or procedure change.
Such precedures and precedure changes =sy be approved f:r : =persry use by
- vo = embers of :he station s:sff, at loss: one of whc= holds s Senior Rea::er Opera:ct's License en the unit (s)..ffected.
Procedures and prosedure chsnart shs!1 be approved prior :n use er within avven day = cf receiving tempursry apprev-al for une by the station Mansger; ur by the Operatinr, Superintendunt, the Technical Servlees Superin:endetu or the Msintenanec Superintendent, as previously designated by the s:ation Manager.
5.
?;oposed :hanget :o the Technical Specifics:1ons shs!! be prepared by a f\\
qualified individus!/orgsnisstion.
The preparatien of each pecpused Tech-l nical Specifica:ians change shall bc reviewee by an individuai/g; cup c:her than the individuallg; cup wnich prepared :he preposed change, but who =ay Amendments 57, 57 & 54 j
6.1-1
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8 be from :he same organization as the individual / group which prepared the l {
Proposed changes to the Technical Specifications shall proposed change.
be approved by the sta: ton Manager.
to station nuctent safety-reinted atructuren, Proponed modi ficat lon*
l symt ema nnd component < nhail be degir,ned by n quallf f ed Individual /
c.
Each much modification shall be reviewed by an Individual /
o rga n ir.n t i on.
individual / group which designed the modification, but group other thsn the who may be from the same organization as the individual / group which Proposed modificatiens to station nuclear designed the modification.
safety-related s:ructures, systems and components shall be approved prior to implementation by the station Manager; or by the Operating Superintendent, I
the Technical Services Superintendent, or the Maintenance Superintendent, as previously designated by the station Manager, Individuals responsible for reviews performed in accordance vi h 6.1.2.1.a, d.
6.1.2.1.b, and 6.1.2.1.c shall be = embers of the s:stion supervisory staff, previously designated by :he station Manager to perform "
Each such review shall include a determination of whether such reviews.
If deemed or not additional, cross-disciplinary, review is necessary.
necessary, such review shall be performed by the appropriate designa:ed station review personnel.
Proposed tests and exportments which affect station nuclear safety and are s.
not addecssed in the FSAA or Technical Specifica: ions shall be reviewed by the Technical Servi-the station Ma, nager; or by the Operating Superintendent,
[
ces Superintendent or the Main:enance Superintendent, as previously desig-nated by :he sta:icn Manager.
Incidents reportable pursuant :o T:chnical Specification 6.6.2.1 and vio-l f.
lations of Technical Specifir.4tions shall be inves:igated and a report pre-pared which evaluates the occurrence and which provides reconmendations to Such repor:s shall be approved by :he station Manager prevent recurrence.
and transmitted to the Vice President, Steam Produe:1on, or his designee; and to the Direc:or of :he Nuclear Saf e:y Reviev Soard.
The sta:Lon Manager shall assure the performance of special reviews and 3
invas: iga: ions, and the prepara:ica and subui:tal of reports : hereon, as requested by the Vice Presisent. Steas Produe: ion.
shall l
h., The station security program, and. implementing procedures,
be reviewed at leas: annually.
Changes determined :o be necessary as a resul: of such review shall be approved by the sta: ion Mar.ager and trans-sitted to :he Vice President, Steam Production, or his designee 3rd to l
the Director of the :iuclear Saf ety keview Board.
shall 1.
The station emergency plan, and inplementing procedures, be reviewed a: least annually.
Changes deter =ined :o be necessary as a result of such review shall be approved by the s:stion Manager and trans-mitted to the Vice President, Steam Preduction, or his designee; and to the Dire::ct of the Wuclear Safety Review Scard.
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The station manager shall assure that an independent fire pro-j.
taction and loss prevention inspection and audi: shall be per-
- f. rned annually utilizing qualified of f-si:e personnel and that shall be an inspection and audi: by a qualified fire consultant nerformed at intervals ac greater than three years.
Amendments 57, 57 & 54 6.1-2 e
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Any other cres of station op3rstion considered appropriate by the NSR3 3
or the Vice President, Stea's Production.
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The station fire protection program and imple=enting procedures at least' h.
once per 24. months.
6.1.3.5 Responsibilities and Authorities Steam Production The USP3 shall report to and advise the Vice President, on those areas of responsibility specified in Specifications 6.1.3.3 and au 6.1.3.4.
Steam Minutes shall be prepared and forwarded to the Vice President, b.
Production, and to the Senior Vice President, Production and Transmission, within 14 days following each formal meeting of the NSR3.
Racords of activities performed in accordance with Specifications 6.1.3.3 c.
and 6.1.3.4 shall be =aintained.
- d... Audir reports encespassed by Section 6.1.3.4 shall be forwarded to the Steam Production, and to the Senior Vice President, Pro,.
Vice President, ductiqn and Tranemission and to the =anagement positions responsible for the areas audited within 30 days of completion of each audit.
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6.1-5 Amendments 57, 57 & 51
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1ASLE 6.1-1 Niel=ue operettag shift lequiremente
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With Fuel to the Three Beacter Vessels tielt 1 er 2 Above l'atto 1 e-J 2 Above Dette 1 er 2 Above thette 1 and 2 Cold h ate 1, 2, Dette 1, 2 ftteleue AEC Cold ShutJowel 18at t Cold s h tdown! IAst!
Cold Shutdowei Ustt Stestdowel Dett 3 and 3 Above and 3 Cold License Seguirassente 3 Cold shutaene 3 Cold slestJowe 3 Atove Cold shutJewe above Cold sh tdowne Cold shutdoes gloatdown A
Senter saector operstar 2
2 2
2 3
2 asector Operater 4
4 4
4 4
3
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b iscessed operater 2
2 2
2 4'
Addittemet Se p trementes 1.
One IIcommed operater per mett shall be to the Centret soon et eli Etee when there le fuel to the reacter veneel.
2.
h e licensed operatore shall be la the Coetrol Roon durina etertup and scheduled orestdown of e Ee.cter.
j 3.
At toast one Itceased operator skalt be to the reactor buildtes when final headttes operettene to the reacter butidtag are la prossess.
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4.
As operater heldlag a Seeler Beacter Operator Itcense and assiseed suo other operational dettee i
shall be se direct therge of refuelles operettoes.
S.
At least one pereen per oblft shall have suffletest tratalog to perform routtee health phyetco g,
g reparemente.
- 1 3
n.
4.
If the computer for a reactor le leoperable for more thee *etsht hours, se operator la eJJttion
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M to those req =tred ebeve shall supplesment the ehtiL crew.
3Cl 7.
A fire brtgede of 5 eseb.re ehe11 6. malacete.d om ette et eli tiese. n.se escludee 3 essa,ere 3
of the stateus operettaa oblf t requirements skrt are required to be present la the coettet roues.
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Hanager j
Oconee Nuclear Station I
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I Administrative Technical Services Operating Maintenance Services Super f eitendent Superintendent Superintendent Superintendent SRO P
itation Safety Performance Operating Maintenance Mechanical
'j' Supervisor Engineer Engineer YI TE,(,FOEQN"")
SRO Engineer I
Site IIcaltli Shift Instrument and P'Isys ic is t Supervisnr3 Electrleal Suo Engineer
'n>
R R
%../
n Chemist Shift g
Personnel
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l OCONEE NUCLEAR STATION STATION ORGANIZATION CHART FIGURE 6.1-1
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Senic: L' ice President Production and Transmission Vice President Nuclear Safety Steam Production Review Board l
Manager Nuclear Production Manager Oconee Nuclear Station
.* Responsible for Fire Protection Program
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A" Nam OCONEE NUCLEAR STATION Qi MANAGEMENT ORGANIZAil0N CHART Figure 6.1-2 6.1-8 Amendments 57, 57 & 54
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g STATION OPERATING PROCE3**'RIS 6,4
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i Specificttien The statien shall be operated and eaintained in accordance with
'Wri: ten procedures vi:h appropriate 6.4.1 ipproved procedures. check-off lists and instructions shall be provided for the following condi: lens:
Nor=al startup, opera: ice and shu:dewn of the ce=piste
- f acility and of all syste=s and co=ponen:s involving nuclear s.
safety of the facility, b.
Ref u'eling operations.
specific and foreseen pctential Actiens taken to ecrrect malfunctions of syste=s or ec=penents involving nuclear c.
safety and radiation levels, including.respenses to alarms, leaks and abnor:21 reactivity changes.
suspected pri=ary systa:
Energency procedu;cs involvin'; potenti,-1 er actual release d.
of radioaccivity.
Preventive or corrective =aintenance which ecuid affect safe:y or radia:icn exposure to persennel.
e.
nucles:
Station survey following an ecrthquake.
f.-
Radicticn control procedures, g.
systems.
Operation of radioactive vaste canagement h.
after loss-of-coolant 1.
Con:rol of pH in rceirculated coolantthat pli vill be measured and the accident.
Procedure shall statt addition of appropriate caustic to ecolant.will co=mence within 30 =inutes after switchover to recircala:icn ecde of core cocling to adjust the pH to a range of 7.0 to S.0 vi:hin 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
Nuclear safety-rela:cd periodic test procedures, j.
Procedures shall in-cuergency ecre cooling syste=s.
k.
Long-ter:
clude provisien for re ote er local operation of system ec ponen:s necessary to establish low pressure injecticn wi:hin 15 minu:es
~ af:c a line break..
1.
Fire Protection Program implementation Quarterly selected drills shall be conducted on site emergency 6.4.2 procedures including assembly preparatory to evacuation off site and a check of the adequacy of communications with off-site.
support groups.
A respiratory protective program approved by the Commission shall be 6.4.3 in force.
6.4-1 Amendments 57, 57 & 54
-*ms-,...
r
m, UNITED STATES NUCLEAR REGULATORY COMMXSSKON 00CXET NOS. 50-269. 50-270 and 50-287 DUKE POWER CCMPANY NOTICE OF ISSUANCE OF AMENCMENTS TO FACILITY _
OPERATING LICENSES The U. S. Nuclear Regula, tory Comission (the Comission) has issued 54 o Facility Operating Licenses Nos. DPR-38, Amendment Nos. 57, 57 and t
OPR-47 and CPR-55, respectively, issued to Duke Pcwer Company which revised Technical Specifications for operation of the Oconee Nuclear Station Unit Nos.1, 2 and 3, located in Oconee County, South Carolina.
The amendments are effective within 20 days of the date of issuance.
The amendment incorporates fire protection Technical Specifications on the existing fire protection equipment and adds administrative controls related to fire protection at the facility. This action is being taken pending comoletien of the Comission's overall fire protection review of the facility.
The application for these amendments cceplies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Ccenission's rules and regulations.
The Comission has made appropriate i
findings as required by the Act and the Comcission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments.
Prior public notice of these amendments was not required since the amendments do not involve a significant ha:ards consideration.
The Commission has determined that the issuance of these amendments will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement, negative declaration, or environmental impact appraisal need not be prepared in connection with issuance of these amendments.
77//?705%
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2-For further details with respect :: :his action, see (1) One a;cifca-tion for amendrents dated March 1,1977, as supplemented Cecember 15, 1977, (2) Amendment Nos. 57, 57 and 54 to Licenses Nos. OFR-38, CFR-47 and CPR-55, respectively, and (3) the Ccmmission's related Safety 5 valuation dated Novemoer 25, 1977.
All of these itee.s are availaole for pubite insoection at the Commission's Public Document Recm,1717 H 5treet, N. W., Washington, O. C.
20555 and at tne Oconee County Library, 201 South Spring, Walhalla, South Carolina 29691.
A copy of items (2) and (3) may be octained upon request addressed to the U. 5. Nuclear Regulatory Commision, Washington, D. C.
20555, Attention:
Director, Division of Ccerating Reactors.
Dated at Bethesda, Maryland, this 13th day of February 1978.
)
FOR THE N', TSAR R5GULA70RY CCMMISSION
/ I ffdtddd L Al s
A. '5cnwencer, Chief Coerating Reactors 3rdnch ?1 Division of Cperating Reactors i
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