ML20044A752
| ML20044A752 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/26/1990 |
| From: | VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20044A751 | List: |
| References | |
| NUDOCS 9007020183 | |
| Download: ML20044A752 (65) | |
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1 .. ATTACHMENT 1 - PROPOSED TECHNICAL SPECIFICATIONS CHANGES ; NORTH ANNA-UNITS 1L AND 2 i I
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l l 1 l 1 j. 1 l l i 9007020183 900626 PDR ADOCK 05000338 P PDC ; i
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l REVISED PAGES FOR CURRENT NORTH ANNA TECHNICAL SPECIFICATIONS ; i i l'
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l I F F s5 I i PROPOSED TECHNICAL SPECIFICATIONS CHANGES i i NORTH ANNA UNIT 1 i l f l-t !- I i l l P
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- 6. A procedure for identifying the authority responsible for the Interpretation of the data and the sequence and timing of administrative events required to initiate corrective action,
- s. The performance of certain surveillance tests at 18, 36, and 60 1 month Intervals to coincide with the normal,18-month refueling I cycles shall be extended by six months' for North Anna Unit 1 seventh cycle only as described in. the licensee's letter dated October 19, 1988. ,
l t, Fire Protection U
.1 VEPCO shall implement and maintain in effect all provisions of the
. approved fire protection program as described in the Final Safety .
Analysis Report for the facility and as approved in the SER dated ) February 1979 subject to tho following provision: ' The licensee' may make changes to the approved- fire l protection -program wlthout prior. - approval of the Commission only if those changes would not adversely affect , the ability to achieve and maintain safe shutdown in the event l
- of a firo, l l
(4 ) The licensee is authorized to receivo from the Surry Nuclear Power l Station Units No.1 and 2, possess, and store Irradiated Surry fuel assemblies containing special nuclear- material, enriched to not more than 4.1% by weight U 235 subject to the following conditions:
- a. Surry fuel assemblies may not be placed In' North Anna Power Station Units No.1 and 2 reactors.
- b. Irradiated fuel shipped to North Anna shall have been removed ,
from the Surry roactors no less than 730 days prior to shipment. 1 l
- c. No more than 500.Surry irradiated fuel assemblies shall bo !
recolved for storage at the North Anna Units No.1 and 2 spent fuel l pool. E. Physica! Protection l The licenseo shall fully implomont and maintain in effect all provisions of I the Commission approved physical security, guard -training and- -l qualification, and safeguards contingency plans including amendments made -l pursuant to provisions- of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR.27817 and 27822) and -l to the authority of 10 CFR 50.90 and 10 CFR 50.54 (p). The plans, which contain Safeguards Information protected under 10 CFR 73.21 are entitled:
" North Anna Power Station Security Plan," with- revisions submitted ,
through February 24,1988; " North Anna Power Station Guard Training ' and Qualification Plan," with revisions submitted through May 14,- 1987;and " North Anna Power Station Safoguard Contingency Plan," with revisions submitted through January 9,1987. Changes made in accordance , with 10 CFR 73.55 shall be imptomented in accordance with the scheduto l set forth thoroin. l l
1 l
.l l
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS . SECTION $2 L 3/4.2 POWER DISTRIBUTION LIMITS l 3/4.2.1 A xlal Fl u x D if f e r e nce . .. . .. . . . . . . .. . .. . . . . . . . .. . . . . . . . .. . .. . .. . . . . .. . . . . .. . . . . . . . . . . .. . . . . . . . 3/4 21 3 / 4 . 2 . 2 H ea t Flu x Ho t C ha n n el Factor.................. .......... ................. ............ ..
. 3/4 25 l l
3 /4. 2. 3 Nuclear Enthalpy Hot Channel Factor................................................ 3/4 29 . . 3 / 4 . 2 . 4 Qu ad ra nt Powe r Tilt R a tlo................................ ............................... .. 3/4 2 12 i 3 / 4 . 2 . 5 D N 8 Pa r a m o t e rs . . . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . .. .. . . . . . . . . .. . . . . . . . . . . . . .. . . . . .. . . .. .. . . ..3/4 .... 2 14 l-3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..................................... 3/4 31 3 /4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM l t i N ST R U M E N TAT I O N . . ... . .. . .. . . . .. . . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . 3/4 . . . . . .3
. . .15......
3/4.3.3 MONITORINGINSTRUMENTATION R adi a tio n M o nilo rin g . . .. . . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . . 3/4 3 35 i M ovable I nco re De to eto rs.. .. . ... .. .. .. .. . . . . .. .. . . .. .. .. .. .. .. . . .. ...... . . .... .. .. .. .. .. .. . 3/4 3 39 i Seism Ic I n stru m en t atio n . . . .. . .. . . .. ... . . . .. . . ... .... . . . ... . . ... . ... ... . .. .. .. .. . . . . .. ..3/4 ... . 3 40 Me toorological in strumentat10n.............................................. ..... ...... 3/4 3 43 Auxiliary Shutdown Panel Monitoring instrumentation.................... 3/4 3 46 Accide nt Monito ring instrument at10n................................................. 3/4 3-49 1 Loo s e Pa rts M onitoring Sy st o m .............. ...... ............................. .... ..... 3/4 3 56 Radioactive Liquid Effluent Monitoring Instrumentation........ .......... . 3/4 3 58 Radioactive Gaseous Effluent Monitoring instrumentation................. . 3/4 3 65 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOU\NT CIRCULATION S tart up a nd Powe r Ope ration . . .. .. .. . . .. .. .. .. ... .. . . .. .. .. .. .. .. .. ... .. .. .. ...... . . . . .. .. . 3/4 41 HotStandby.......................................................................................... 3/4.42 1 Shutdown............................................................................................... 3/4 43 I 3/4 44 l so l a t ed Le o p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i so la t c d Loop S t a rt u p. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 45. NORTH ANNA UNIT 1 IV Amendment No. l
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l l l INDEX i t 1 BASES SECTION Egg . 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINECYCLE................................................................................. B 3/4 7 1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION........... B 3/4 7 4 3/4.7.3 COMPONENT COOLING WATER SUBSYSTEM....................................... B 3/4' 7 4 1 3/4.7.4 S E RVI C E WAT E R SYST EM . .. .. . .... . . .. . . ... . .. . . ... . ... . . ... . .. ...... . .. . . . .. . .. . . . . .. . . . . . B 3/4 ' 7 4 3/4.7.5 U LT I M AT E H E AT S I N K . . . . ... . .. .. . ... .. .. . . . .... . . .. ... . . . .. .. .. . . .. . . . . .. .. . . .. . . . .. . . . . .. . . B 3/4 7 5 3/4.7.6 F LOO D P R OT E CTI ON .. . . .. . . . .. ... . . . ..... .. .... . . . . .. . ... .... . . .. . . .. . . . .. . .. . . .. .. . . . .. . . .. . . . B 3/4 7 5 - 3/4.7.7 CONTROL ROOM EMERGENCY HABITABILITY...................................... B 3/4 7 5 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM......................................... B 3/4 7 5 3/4.7.9 RE SiDUAL HEAT REMOVAL SYSTEMS.................................................. B 3/4 7 6 3/4.7.10 HYD R AU LlO S N U B B E RS. .......... . ....... ........ ....... .... ............... ................. . B 3/4 7 6 3/4.7.11 S EALE D SOU RC E CONTAMINATION....................................................... B 3/4 7 7 ' 3/4. 7.12 SETTLEMENT OF CLASS 1 STRUCTURES.............................................. B 3/4 7 7a j 3/4.7.13 GROUNDWATER LEVEL SERVICE WATER RESERVOIR....................... B 3/4 7 9 3/4.8 ELECTRICAL POWER SYSTEMS . 3/4.8.1 A .C . S O U R C E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3 /4 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS............................................. B 3/4 8 1 3/4.9 REFUELING OPERATIONS 3/4.9.1 BO RO N CON C ENTR ATION............................................. ......................... . B 3/4 9 1 1 1 3/4.9.2 I N ST R U M E NTAT I O N . . . . . . . . . . . . . ... . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . .. . . . . . . B 3/4 9 1 NORTH ANNA - UNIT 1 XV Amendment No. t
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t NORTH ANNA UNIT 1 3/4 7 84 Amendment No. 1
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i ESTRUMENTATION i IRc.ES t f 3/4.3.3.6 POST ACCIDENT INSTRUMENTATION The OPERABILITY of the post accident instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables following an accident. 3/4.3.3.9 LOOSE PARTS MONITORING SYSTEM OPERABILITY of the Loose Parts Monitoring System provides assurance that loose parts within the RCS will be detected. This capability is designed to ensure that loose parts will not collect and create undesirable flow blockages. NORTH ANNA UNIT 1 B 3/4 3 3 Amendment No. l
I ( PLANT SYSTEMS E i 3/4.7.13 GROUNDWATER LEVEL-SERVICE WATER RESERVOIR A program to monitor groundwater levels in the area of the service water reservoir has been established to ensurs that the Integrity of the service water reservoir embankments and pumphouse is maintained, , Groundwater threshold levels have been established based on historical groundwater data available in 1977. These levels are sulliclently conservative to ensure that the service water reservolt and pumphouse will perform their intended function An engineering evaluation will be performed if these thrashold values are exceeded, to determine if there is any substantive cause to believe that any aspect of the service water reservoir, dike or pumphouse will not perform !!s intended function. A conclusion to this effect, and the appropriate corrective actions to be performed, will be reported to the Commission,- The groundwater threshold lovels are porlodically reviewed to determine whether a changing groundwater environment warrants a change in threshold levels, NORTH ANNA UNIT 1 B 3/4 '7-9 Amendment No,
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NORTH ANNA UNIT 1 83/4710 Amendment No.
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^l ADMINISTRATIVE CONTROLS j
- o. The management position responsible for health physics shall have direct access to that onsite individual having responsibility for overall facility management. Health physics i personnel shall have the authority to coaso any work activity when worker safety is j jeopardized or in the event of unnocessary personnel radiation exposures.
FACILITY STAFF 6.2.2 The Facility organization shall be as shown in the UFSAR. j
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.21.
1
- b. At least one licensed Reactor Operator shall be in the control room when fuel is in the reactor, in addition, while the unit is in MODES 1,2,3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room.
- c. A health physics technician # shall be onsite when fuol is in the reactor,
- d. ALL CORE ALTERATIONS shall be observed and directly supervised by olther a licensed -
Senior Roactor Operator or Senior Reactor Operator Limited to Fuel Handling who has no other concurrent responsibilillos during this operation. l i
# The health physics technician composition may be loss than the ml'itmum requirements for a (
period of timo not to exceed 2 hours in order to accommodato unexpected absence provided l Immodlate action is taken to fill the required positions. l NORTH ANNA UNIT 1 - 61a Amendment No. l i l^
-/.
u ADMINISTRATIVE CONTROLS K. Review of overy unplanned onsite release of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to provent recurrence and the forwarding of those reports to the Vice President Nuclear and the offsite management posltlon responsible for independent / operational event review. l Review changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL
- m. Review of the Fire Protection Program and implementing procedures and shall submit recommended changes to the Station Manager.
ALRHORITY 6.5.1.7 The SNSOC shall:
- a. Provide.writton approval or disapproval of items contidorod under 6.5.1.6(a) through (c) abovo, SNSOC approval shall be cortified in writing by an Assistant Station-Managor,
- b. Rendor dolorminations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (0) above constitutes an unrevolwod safety question,
- c. Provido written notification within 24 hours to-the Vice President Nuclear- and the offslte management position responsible for Independent / operational event review of g disagrooment betwoon the SNSOC and the Station Manager; however, the Station Manager shall have responsibility for rosolution of such disagrooments pursuant to 6.1.1 above.
RECORDS 6.5.1.8 The SNSOC shall maintain writton minutos of each mooting and copios shall bo provided to the Station Managor, Vice President Nuclear and the offsite management position responsible for indopondent/ operational ovent review. 6.5.2 INDEPENDENT / OPERATIONAL EVENT REVIEW (IOER) GROUP FUNCTION 6.5.2.1 The IOER Group shall function to provido Indopondent review of designated activities in the areas of:
- a. Nuclear power plant operations .
- b. Nuclear engincoring
- c. Chemistry and radiochemistry
- d. Metallurgy
- o. Instrumentation and control
- f. Radiological saloty
- g. Mechanical and cloctrical engincoring
- h. Administrativo controls and quality.assuranco practicos
- 1. Other appropriato fields associated with the uniquo characteristics of the nuclear power plant NORTH ANNA UNIT 1 67 Amendment No.
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l ADMINISTRATIVE CONTROLS _
- c. Surveillance and test activities of safely related equipment.
- d. Security Plan implementation,
- e. Emergency Plan implementation.
- f. Fire Protection Prograrn implementation.
9 PROCESS CONTROL PROGRAM implementation.
- h. OFFSITE DOSE CALCULATlON MANUAL Implementation.
- l. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1. June tS74 and Regulatory Guide 4.1, Revision 1 April 1975.
o 6.8.2 Each procedure of 6.8.1 above, except 6.8.1.d,6.8.1.e, and 6.B.'t.f and changes thereto, l 1 shall be reviewed and approved by the SNSOC prior to implementation and reviewed periodically ; as set forth in administrative procedures. Procedure of 6.8.1.d, 6.8.1.e, and 6.8.1.f shall be ' reviewed and approved as per 6.5.1.6.1, 6.5.1.6.l ond 6.5.1.6.m. SNSOC approval shall be certified in writing by as Assistant Station Manapr. 6.8.3 Temporary changes to procedures of 6.8.1 above may be made provided:
- a. The intent of the original procedure is not altered,
- b. The change is approved by two members of the plant supervisory staff, at least one of whom holds a Senior Reactor Operator's License on the Unit affected.
- c. The change is documented, reviewed, and approved by the SNSOC within 14 days l of implementation. SNSOC approval shall be certifled in writing by an Assistant Station Manager.
6.8.4 The following programs shall be established, implemented, and maintaineu:
- a. Primarv Coolant Sources Outside Containment A program to reduce leakage from those portions of systerim outside coittainment .
that could contain highly radioactive fluids'during a serious translent nr accident to as low as practical levels, The systems include the recirculation spray, safety injection, chemical and volume control, gas stripper, and hydrogen recombiners. The program shall include the following: (l) Prevontive maintenance and periodic visual inspection requirements, and (II) Integrated leak test r0quirements for each system at refueling cycle intervals or less. NORTH ANNA UNIT 1 6-13 Amendment No, i
I ADMINIST RATIVE CONT ROLS (Continured) SEICIALREPORTS 6.9.2 Special reports shall be submittod to the Regional Administrator, Roglon 11, within the timo porlod specilled for each report. Those reports shall be submittod pursuant to the requirement of the applicable specification:
- a. Inservico Inspection Reviews, Specihcation 4.0.5, shall be reported within 90 days of completion.
- b. MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.
- c. RADIATION MONITORING INSTRUMENTATION. Spocification 3.3.3.1, Tablo 3.3 6, Action 35.
- d. SEISMIC INSTRUMENTATION. Specifications 3.3.3.3 and 4.3.3.3.2.
- c. METEOROLOGICAL INSTRUMENTATION. Specification 3.3.3.4.
- f. doloted
- g. LOOSE PARTS MONITORING SYSTEMS. Spocificatbn 3.3.3.9.
- h. REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY. Specification 3.4.0,
- l. OVERPRESSURE PROTECTION SYSTEMS Specificatbn 3.4.9.3.
j . EMERGENCY CORE COOUNG SYSTFMS. Spocification 3.5.2 and 3.5.3.
- k. SETTLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.
- l. GROUND WATER LtEVEL SERVICE WATER RESERVOIR, Specification 3.7.13.
- m. doloted
- n. RADIOACTIVE EFFLUENTS. Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4 and 3.11.4.
- o. RADIOLOGICAL ENVIRONMENTAL MONITORING. Spocification 3.12.1.b.
- p. SEALED SOURCE CONTAMINATION. Specification l.7.11.1.3.
q REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. Specificatbn 4.4.10. For any abnormal degradation of the structural intogrity of the reactor vessel or the Roactor Coolant System pressuto boundary dotected during the porlormanco of Specification 4.4.10, an inillal toport shall bo submitted within 10 days attor dotection and a dotalled report submitted within 90 days aflor the completion of Specification 4.4.10. NORTH ANNA UNIT 1 0 21 Amondrnent No.
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b i h I i i i f i r l i k i PROPOSED TECHNICAL SPECIFICATIONS CHANGES : i NORTH ANNA UNIT 2 ! f e I
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12- l s (l) Containment pressure from 0 psia to three times the design pressure of the containment no later than the implementation schedule of NUREG 0737,
- 1) Contalnment water level from (1) the bottom to the top of the containment sump, and (2) the bottom of the containment to a j level equivalent to 600,000 gallons of water no later than the implementation schedule of NUREG 0737.
(lli) Containment atmosphere hydrogen concentration from 0 to 10 ) volume percent shall be installed no later than January 1, ! 1983, and the hydrogen sampling system to be used in the l interim shall remain in effect until January 1,1983; (lv) Containment radiation up to 107 R/hr. no later than the second refueling outage. (v) Noble Oas effluent from envh potential release point from normal concentrations to 105 pCl/cc (Xe 133) no later than January 1,1983. l VEPCO shall also provide capability for continuous sampling and for onsite analysis of the radiolodine and particulate ; effluent samples no later than January 1,1983. (j) Inndannato Core Coolina Instruments (Section 22 3 Item II. F.2) , VEPCO shall install and demonstrate the operability of additional Instruments or controls needed to supplement installed equipment in , order to proviue unambiguous, easy to interpret Indication of Inadequate core cooling at tha first outage of sufficient duration but no later than July 1,1982. : (22) The license is authorized to receive from the Surry Nuclear Power Station Units No.1 and 2, possess, and store Irradiated Surry fuel assemblies containing special nr's ; material, enriched to not more than 4.1% by weight U 235 subject to the tot 5 wing conditions:
- a. Surry fuel assemblies may not be placed in the North Anna Power Station Units No.1 and 2 reactors,
- b. Irradiated fuel shipped to North Anna shallhave been removed from the Surry reactors no less than 730 days prior to shipment,
- c. No more than 500 Surry irradiated fuel assemblies shall be teceived i for storage at the North Anna Units No.1 and 2 spent fuel pool.
1
128* (23) Fire Protection I VEPCO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated February 1979 subject to the following provision: The licensee may may changes to the approved fire protection program without prior approval of the Commission only if those changes would , not adversely affect the ability to achieve and maintain safe shutdown ! In the event of a fire, s l i f [ r a L f f I h
INDEX UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION BE 3L4.2 POWER DISTRIBUTION LIMITS 3 / 4 . 2 .1 A xial Flu x Ditf or e neo . .. . .. .. ... . .. . ... .. . .. . ... .. ....... ... .. .. .. .. ... . .. . ... .. ... .... ... ... 3/4 21 3 / 4 . 2. 2 Heat Flu x Hot C hannel Factor............................................................ 3/4 25 3 /4. 2.3 Nucloar Enthalpy Hot Channel Factor................................................ 3/4 29 3 / 4 . 2. 4 Qu ad ra nt Power Till R a t!o................................................................. 3/4 2 12 3 / 4 . 2 . 5 D N B Pa r am o to r s .. .. .. .. .. . . .. .. . . .. . . .. . . . . . . . . .. .. .. .. . . .. .. .. .. . . .. . .. . .. .. .. . . . . .. . . . . .. . . . . 3/4 2 15 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION..................................... 3/4 31 3 /4.3.2 ENGINEERED SAFETY FEATURE ACTUAllON SYSTEM I N S T R U M E N T AT IO N . . .. . . .. .. . . . . .. . . .. ... . . . . . . .. . . . . . .. . . . . ... .... . . . . . . . . . ... . . . . .. . . . .. . . . . 3/4 3 15 3/4.3.3 MONITORINGINSTRUMEt#ATION R a di a t io n M o ni to r in g . . .. . . . . . . . . . . .. . . . .. . .. . . . . . . . . . . .. . . . .. . . . . . . . . . . .. . . . . . . . . . . . . .. . . . .. . . 3/4 3 38 M ovabl o I neer o D e t octor s.... ............ .. .. .. .. .. .. . . .. .... .. .... .. .. ...... .. .. .. . . .. ..... 3/4 3 42 Auxiliary Shutdown Panol Monitoring instrumentation.................... 3/4 3 43 Accidont Monitoring instrumonIation................................................. 3/4 3 46 i Radioactivo Liquid Ellluont Monitoring Instrumentation................... 3/4 3 53 Radioactivo Gasoous Elfluent Monitoring Instrumontation................. 3/4 3 60 E4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS AND COOLNR CIRCULATION S ta rt up and Powor Opo r at10n .. ...... .. .. .. .. ..... ........ .. .. . ... .. .. ... .. .. . . .. .. .. .. .. . . . 3/4 41 HotStandby........................................................................................... 3/4 42 Shutdown.............................................................................................. 3/4 43 I s o l a t od Lo o p . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3/4
. . . . . . . .44 I sola t o d Lo t p S t a r t u p. .. .. . .. . . . . .. . . . . . . . . . .. . . .. . .. .. .. . . .. . . .. . . . .. .. . . . . .. . . . . . .. . . . . . .. . . .. . . 3/4 45 NORTH ANNA UNIT 2 IV Amendment No.
1 INDEX UMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMEhrTS SECTO4 ESE 3'4.8 ELFCTRICAL POWER SYSTEMS 3/4.8.1 AC. SOURCES Ope r at in g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 / 4 81 Shutdown.........,,...................................................m............................... 3/4 8 10 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A. C. Distribution Ope rating ............................................................. 3/4 8 11 A.C. Dist ribution S h utdown.................................................... ........... 3/ 4 8 12 D. C. Distributio n Opo rating ............................................................. 3 /4 8 13 D. C. Dis tribu tio n S h utdown... .......................................................... 3/4 8 15 Containment Ponotration Conductor Overcurrent Pr o l o ct lv o De vic e s . . . . . . . . . ... . . . . . . . .. .. . . . . . . . .. . . . .. . .... .. ... .. . .. . . .. . .. .. . . . .. .. . . . .. . . . . . . 3 / 4 Motor Operated Valvos Thermal Overload Protection a n d/o r B yp as s D evic e s . . .. . . . .. . . . . . . . . . . . . .. . . .. . .. .. . . .. . . .. . . .. . . .. .. ... .. .. .. .. . . .. .. .. .. . . 3 / 4 8 21 NORTH ANNA UNIT 2 Vill Amendment No.
INDEX f BAsrs __ SECTON DE i 3/4.7 PLANT SYSTEMS 3/4.7.1 B 3/4 7 1 T U R B I N E C YC L E . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.. ....... B 3/4 7 4 , 3/4.7.3 COMPONENT COOLING WATER SUBSYSTEM... ........ B 3/4 7 4 > 3/4.7.4 SE R VI C E WAT E R S YST E M . . . ............ . ..... .. . ... . . .. . . . .. ........ . . ..... ..... .. . . ... .. . . B 3/4 7 4 ; 3/4.7.5 U LT IM AT E H E AT S I N K .. .. . . . .... .. .. . .. .. .. . ... .. .. .. . . .. ... .. ... . .. .. . . . . .. . . .. . . . . . . . . . .B . . .3/4 7 5 3/4.7.6 FLOO D P R OT E C T10N ..... .. .... . . ... .. ..... .. .. .. . . . .. . .. . . ... . . .. ... . .. . .. . . . .. . . . ..... . . . ... .. B 3/4 7 5 3/4.7.7 CONTROL ROOM EMERGENCY HABITABluTY...................................... B 3/4 7 5 ; 3/4.7.8 SAFEGUARDS AREA VENTILATION SYSTEM......................................... B 3/4 7 5 3/4.7.9 RESIDUAL HEAT REMOVAL SYST EMS.................................................. - B 3/4 7 6 ! 3/4.7.10 H Y D R A U LI C S N U B B E R S . ... . . . . .. . .. . . . .. . .. . . . . . . .. . . ... . .. .. . . .. . . .. . . .. ... . . .. .. . . . ... . . . . . B 3/4 7 6 : 3/4.7.11 SEALE D SOU RC E CONTAMINATION....................................................... B 3/4 7 7 , 3/4.7.12 SETT LEMENT OF CLASS 1 STR UCTU RES.............................................. B 3/4 7 7 3/4.7.13 GROUNDWATER LEVEL. SERVICE WATER RESERVOIR....................... B 3/4 79 o ;
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314.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 and 3/4.8.2 AC. AND D.C. POWER SOURCES AND : l D I ST RI B UT l ON .. ......... ...... ... .... ... ... ... .......... .. ... ... ... ....... ... ...... B 3/4 8 1 i 1 l l f l i l r NORTH ANNA UNIT 2 Xlli Amendmont No.
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i . Pl. ANT SYSTEMS 1%SES 3'4.7.13 GROUNDWATER LEVEL-SERVICE WATER RESERVOIR A program to monitor groundwater levels in the area of the service water reservoir has been 9stablished to ensure that the Integrity of the service water reservoir ombankments and pumphouse is maintained. Groundwater threshold levels have been established based on historical groundwater data available in 1977. Those levels are sufficiently conservativo to ensure that the service water reservoir and pumphouse will perform their intended function. An engineering evaluation will bo performed if these threshold values are excooded, to determine if there is any substantive cause to believe that any aspect of the service water reservoir, dike or pumphouse will not perfonn its intended function. A conclusion to this offect, and the appropriato corrective actions to bo performed, will be reported to the Commission, ! The groundwater threshold levels are periodically reviewed to determine whether a changing groundwater environment warrants a change in threshold levels, i 1 i 1 NORTH ANNA UNIT 2 B 3/4 7 9 Amendment No.
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i 1 1 - NORTH ANNA UNIT 2 83/4710 . AmendmentNo. oio + ,
ADMINISTRATIVE CCNTROLS
- e. The management position responsible for health physics shall have direct access to that onsite Individual having responsibility for overall facility management. Health physics personnel shall have the authority to cease any work activity when worker safety is jeopardized or in the event of unnecessary personnel radiation exposures.
FACILITY STAFF l 1 6.2.2 The Facility organization shall be as shown in the UFSAR.-
- a. Each on duty shift shall be composed of at least the minimum shift crew composition shown In Table 6.21.
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- b. At least one licensed Reactor Operator shall be in the control room when fuel is in the -
. reactor, in addition, while the unit is in MODES 1,2, 3 or 4, at least one licensed Senior Reactor Operator shall be in the Control Room,
- c. A health physics ochnician# shall be onsite when fuel is in the reactor.
- d. ALL CORE ALTERATIONS shall be observed and directly supervised by either a licensed-Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling who has = ,
no other concurrent responsibilities during this operation. 4 i
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- The health physics techniciari~ coin ~ position may be less than the minimum requirements for.a l !
per_ lod of time not to exceed 2 hours in order to accommodato unexpected absence provided - Immediato action is taken to fill the required positions. ! NORTH ANNA UNIT 2 61a Amendment No. i
l ADMINISTRATIVE CONTROLS K.- Review of every unplanned onsite roloaso of radioactive material to the environs including the preparation of reports covering evaluation, recommendations and i disposition of the corrective action to p ovent recurrence and the forwarding of those' -J reports to the Vice President Nuclear and the offsite management position responsible i for independent / operational event review, i
- 1. Review changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE 'l CALCULATION MANUAL l
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- m. Review of the Fire Protection Program and Implomonting procedures and shall submit. l recommended changes to the Station Manager.
AlRHORITY 'l 6.5.1.7 The SNSOC shall:
- a. Provide written approval or disapproval of items considorod under 6.5.1.6(a) through ,
(c) above, SNSOC approval shall be certilled in writing by an Assistant Station Manager,
- b. Rondor determination ,n writing with regard to whether or not each item considered under 6.5.1.6(a) throusn (0) abovo constitutos an unrevolwod safety question,
- c. Provido written notification within 24 hours to tho Vice President Nuclear and the offsite management position responsible for Independent / operational event review of; -
disagrooment between the:SNSOC' and the Station. Manager; however, the Station Manager shall have responsibility for resolution of such disagrooments pursuant to 6.1.1 above. HICCBDifi < 6.5.1.8 The SNSOC shall maintain written minutos of each mooting and copios chall be provided j to the Station Manager, Vice President-Nuclear and the offsito managomont position responsible for Independent / operational event review. 1 6.5.2 INDEPENDENT / OPERATIONAL EVENT REVIEW (IOER) GROUP FUNCTION ! l 6.5.2.t The IOER Group shall function to provide independent review of designated activ@s in a the areas of: 1
- a. Nuclear power plant operations
- b. Nuclear engineering
- c. Chemistry and radiochemistry u
- d. Motallurgy
- e. Instrumentation and control -
- f. Radiological safety j
- g. Mechanical and electrical engineenng
- h. Administrativo controls and quality assurance practices
- i. Other appropriato fields associated with the unique characteristics of the ntclear power plant NORTH ANNA UNIT 2 68 Amendment No.
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- c. Surveillance and test activities of safety related equipment,
- d. Security Plan implementation.
- e. Emergency Plan implementation.
, f. Fire Protection Program Implementation.- l g. PROCESS CONTROL PROGRAM implementation. ' 4
- h. OFFSITE DOSE CALCULATION MANUAL implementation. ,
- l. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide' 4.1, Revision 1, April 1975. !
6.Dr och procedure of 6.8.1 above, except 6.8.1.d 6.8.1.e and 6.8.1.f and changes thereto, l ' shall & gilewed and approved by the SNSOC prior to implementation and reviewed periodically as set urth in administrative procedures. Procedure of 6.8.1.d, 6.8.1.e and 6.8.1.f shall be _ r reviewed and approved as per 6.5.1.6.1, 6.5.1.6.j, and 6.5.1.6.m. SNSOC approval shall be' certified in writing by as' Assistant Station Manager. 6.8.3 Temporary changes to procedures of 6.8.1 above may be mado provided: , 1
- a. The intent of the original oroceduto is not. altered, j
- b. The change is approved by two members of the plant supervisory staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected. i
- c. The change is documented, reviewed, and approved by the SNSOC within 14 days of implementation. SNSOC approval shall be certified in writing by an Assistant Station Manager. '
6.8.4 The following programs shall be established, implemented, and maintained: l
- a. Primarv Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment ,
that could contain highly radioactive fluids during a serious transient or accident ' to as low as practicallevels. The systems include the recircu!ation spray, safety , l Injection, chemical and volume control,' gas stripper, and hydrogen recombiners. l The program shall include the following: (l) Preventive maintenance and periodic visual Inspection requirements, and. ] 1 (ll) Integrated leak test requirements for each system 'at refueling cycle j intervals or less. NORTH ANNA UNIT 2 6 14 Amendment No.
I ADMINISTRATIVE CONTROLS SPECIAL REPORTS t 6.9.2 Special reports shall be submitted to the Regional Administrator, Region 11, within the time period specified for each report.. Those reports shall be submitted pursuant to the requirement of the applicable specification:
- a. Inservice inspection Reviews, Specification 4.0.5, shall be reported within 90 days of completion.
- b. MODERATOR TEMPERATURE COEFFICIENT. Specification 3.1.1.4.
- c. deleted .
- d. RADIATION MONITORING INSTRUMENTATION. Specification 3.3.3.1, TABLE 3.3-6 Action 35. ,
- e. REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY. Specification 3.4.8.
- f. OVERPRESSURE PROTECTION SYSTEMS. Specification 3.4.9.3.
O. EMERGENCY CORE COOLING SYSTEMS. Specification 3.5.2 and 3.5.3.
- h. SETTLEMENT OF CLASS 1 STRUCTURES. Specification 3.7.12.
- l. GROUND WATER LEVEL SERVICE WATER RESERVOIR. Specification 3.7.13.
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- k. deleted I. RADIOACTIVE EFFLUENTS. Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4 and 3.11.4.
- m. RADIOLOGICAL ENVIRONMENTAL MONITORING, Specification 3.12.1.b.
- n. SEALED SOURCE CONTAMINATION. Specification 4.7.11.1.3.
- o. REACTOR COOLANT SYSTEM STRUCTURAL INTEGRITY. Specification 4.4.10. For any- .
abnormal degradation of the structural integrity of the reactor vessel or the Reactor Coolant System pressure boundary detected during the performance of Specification 4.4.10, an Initial report shall be submitted within 10 days after detection and a detailed report submitted within 90 days after the completion of Specification 4.4.10.
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- p. CONTAINMENT STRUCTURAL INTEGRITY. Specification 4.6.1.6. For any abnormal ,
degradation of the containment structure detected during the performance of Specification 4.6.1.6, an Initial report shall be submitted within 10 days after completion of Specification 4.6.1.6. A final report, which includes (1) a description of the condition of the linor plato-and concrete, (2) Inspection procedure, - (3) the tolerance on cracking, and (4) the corrective actions takon, shall be submitted within 90 days ator the completion of Specification 4.6.1.6. NORTH ANNA UNIT 2 6 21 Amendment No. i
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k l 1 e i i CHANGE PAGES FOR NORTH ANNA MERITS TECHNICAL SPECIFICATIONS i
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MERITS FORMAT , THIS SPECIFICATION WILL BE RELOCA'IED.TO CHAPTER.16 (TECHNICAL ~ REQUIREMENTS) SECTION16.2 OF THE UFSAR PER THE MERITS PROGRAM. THE; TECHNICAL SPECIFICATION BASES WILL BE INCLUDED IN UFSAR SECTION 9.5.1. i
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- ATTACHMENT 2 i
DISCUSSION AND SAFETY. EVALUATION - - q l L ; [ s !
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Discussion and Evaluation Banin for the Prooosed Change Generic Letter 8610 requested that licensees incorporate Fire Protection Programs into their UFSARs, and upon completion apply for an amendment to 1) replace current licensing conditions regarding fire protection with a new standard condition, and 2) remove unnecessary fire protection Technical Specifications. Generic Letter 88-12 3rovides additional guidance for the preparation of a license amendment request to mplement Generic Letter 8610. Qheuanlon of Pronosed Changen The proposed changes have been developed in accordance with the guidance contained in NRC Generic Letter 8610 and 8812, and are consistent with NRC and industry efforts to simplify the Technical Specifications. The proposed changes include the following actions: (1) Add the NRC standard fire protection license condition to each unit's Operating License (License Condition 2.D(3)t for Unit 1 and 2.C.(23) for Unit 2), (2) Remove fire protection requirements from the Technical Specifications, and (3) Remove the Technical Specification Bases - sections relating to fire protection. Attachment 1 provides the proposed Technical Specification change pages. UFSAR Section 16.2 was created to contain the fire protection requirements currently - contained in the Technical Specifications. Information contained in the Technical Specification Bases is now included in UFSAR Section 9.5.1, No changes have been made to the technical content by this administrative relocation, per the requirements of Generic Letter 8812. Compliance with the fire protection requirements will be assured by maintaining these requirements in appropriate plant procedures and the UFSAR. This change offers additional flexibility in updating and maintaining the fire protection program. The proposed changes relocate the requirements from the Technical Specifications to the UFSAR. Since no technical changes are involved, the relocation of the requirements is viewed as administrative in nature. Summary The proposed Technical Specification change implements Generic Letter 86-10 and 88-12. Sections of the UFSAR have been updated to reflect the fire protection program, and station administrative procedures are being revised. Fire protection program requirements remain an integral part of Station operations regardless of where they are located.
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ATTACHMENT 3 10 CFR 50.92 EVALUATION - E a t
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v - l No Significant Hazards Analysis The proposed change has been evaluated in accordance with the standards of 10CFR50.92(c) and has determined that operations in accordance with these changes
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l (1) Involve a significant increase in the probability or consequences of an accident j previously evaluated. The requirements for the fire protection program have not been ' changed by this proposed change. Relocation of these requirements into the UFSAR l and plant procedures does not negate or diminish any portion of the fire protection i program. Therefore, the same conditions exist as before the change and there is no significant increase in the probability.or consequences of ~an' accident previously.- . evaluated. (2) Create the possibility of a new or different kind of accident from any accident-previously evaluated. The requirements for the fire protection program have not been changed by the proposed change. No-new or. modified requirements have been Introduced. Therefore, the same conditions exist as before the change and the possibility for a new or different kind or accident from any evaluated.has not been created. (3) Involve a significant reduction in the margin of safety. Implementation of the requirements of the fire protection program is assured by 8JFSAR requirements and plant procedures. Since the program remains the same and is implemented the same, there is no reduction in the margin of safety. 1 4 l
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