Text

Forwards marked-up Tech Specs as Proposed Revs for Full Power Ol,Including Corrections of Typos & Inconsistencies Between Index & Text,Deletions/Clarifications of Footnotes & Changes to Wording
	ML20212G705
Person / Time
Site:	Vogtle
Issue date:	02/27/1987
From:	Gucwa L; GEORGIA POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	SL-2080, NUDOCS 8703050394
	Download: ML20212G705 (36)
	v • d • e

_ _ _ - - - _.

p Georgia Power Cornpw.

- 333 Piedmont Avenue

- Attata. Georgi 2 30308 Ltphone 404 5264526 Mailing Address:

Post Office Box 4545 Atlanta, Georgia 30302 Georgia Power L T. Gucwa the southem electrc system Manager Nuclear Safety and Licensing SL-2080 0120m February 27, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 NRC DOCKET 50-424 OPERATING LICENSE NPF-61 V0GTLE ELECTRIC GENERATING PLANT UNIT 1 PROPOSED REVISIONS TO FULL-POWER TECHNICAL SPECIFICATIONS Gentlemen:

We have. reviewed the Technical Specifications that were issued with the VEGP Unit 1 low-power operating license on January-16, 1987.

As a result of this review we have compiled a list of proposed revisions for the NRC's consideration when issuing the Technical Specifications for the full-power license.

These proposed revisions are described below and appropriately -

marked-up Technical Specifications are enclosed.

The changes can be placed in the following categories:

1.

Editorial changes such as corrections of typographical errors or inconsistencies between the index and text have been made on pages:

I, IV, V, VI, VIII, XIV, XVI, XVIII, XIX, XXII, XXIII, 3/4 3-63, 3/4 3-79, 3/4 4-26, 3/4 4-28, 3/4 4-31, 3/4 7-18, 3/4 7-24, 3/4 8-6, and 3/4 4-11 2.

Deletions of footnotes that will no longer be applicable after the issuance of the full-power license have been made on pages 3/4 4-10, 3/4 7-4, 3/4 7-9, and 3/4 9-1.

Clarifications or explanations which do not change any LCO, applicability, 3.

action, or surveillance requirement have been proposed for pages 3/4 3-60, 3/4 3-72, 3/4 3-76, 3/4 4-33, 3/4 7-10, and 3/4 8-3 as described below:

(a) The word " wide" was replaced with the word "high" for Item 13 of Table 3.3-8 on page 3/4 3-60.

This makes the item consistent with other Technical Specifications which apply to this instrument.

RO )

O i

Y j 8703050394 870227ADOCK 05000424 ql PDR PDR{

P

k Georgia Power h U. S. Nuclear Regulatory Commission February 27, 1987 Page.2 (b). Erroneous instrument numbers on pages 3/4 3-72, 3/4 3-76, and 3/4 4-33=are corrected.

Missing instrument numbers on page 3/4 7-10 are added.

(c) - The phrase "on a staggered test basis". was deleted from page 3/4 8-3

~

because the test frequencies as stated in Table 4.8-1 are intended to be applied on a "per diesel generator" basis. The definition of staggered. test basis could be misapplied to this Technical Specification as requiring test frequencies to be determined on a "per nuclear unit" basis.

4.

.-A change to the action requirement for the Fuel Handling Building Ventilation System affecting pages 3/4 3-24, 25, and 27 has been

_ proposed.

This change is consistent with the relationship of this system to the safety analysis as explained in the bases on page B3/4 9-3.

GPC requests that the NRC consider incorporating these proposed, revisions when issuing-Appendix A to the full-power license.

If the need for additional revisions is recognized, they will be brought to your immediate attention.

Should you have any questions, please contact this office at any time.

Sincerely, fg~

L. T. Gucwa JH Enclosures l

i

. roons

Georgia Power A U. S. Nuclear Regulatory Commission February 27, 1987 Page 3 c(w):

-Georgia Power Company Mr. R. E. Conway Mr. J. P. O'Reilly -

Mr. G. Bockhold, Jr.

G0-NORMS Southern Company Services Mr. J. A. Bailey Shaw, Pittman, Potts & Trowbridge Mr. B. W. Churchill, Attorney-at-Law Troutman, Sanders, Lockerman & Ashmore Mr. J. E. Joiner, Attorney-at-Law U. S. Nuclear Regulatory Commission Dr.- J. N. Grace, Regional Administrator Mr. H. H. Livermore, Senior Resident Inspector-Construction, Vogtle Ms. M. A. Miller, Licensing Project Manager, NRR (2 copies)

Mr. J. F. Rogge, Senior Resident Inspector-0perations, Vogtle Georgians Against Nuclear Energy Mr. D. Feig Ms. C. Stangler l

l 700775

INDEX

[

DEFINITIONS SECTION PAGE 1.0' DEFINITIONS 1.1 ACTION................

1-1 1.2-ACTUATION LOGIC TEST.........................................

1-1 1.3 ANALOG CHANNEL OPERATIONAL TEST...............................

1-l' 1.4 AXIAL FLUX DIFFERENCE.........................................

1-1 1.5 CHANNEL CALIBRATION...........................................

1-1 1.6 CHANNEL CHECK.................................................

1-1 1.7 CONTAINMENT INTEGRITY.........................................

1-2

1. 8 CONTROLLED LEAKAGE............................................

1-2 1.9 COREALTERATIONS.............................................

1-2 l 1.10 DOSE EQUIVALENT I-131........................................

1-2 1.11 E-AVERAGEDISINTEGRATIONENERGY..............................

1-2 1.12 ENGINEERED SAFETY FEATURES RESPONSE TIME.....................

1-3 1.13 FREQUENCY N0TATION...........................................

1-3

(

1.14 GASE0US WASTE PROCESSING SYSTEM..............................

1-3 1.15 IDENTIFIED' LEAKAGE...........................................

1-3 1.16 MASTER RELAY TEST.............................................

1-3 1.17 MEMBER (S) 0F THE PUBLIC......................................

1-3 1.18 0FFSITE DOSE CALCULATION MANUAL..............................

1-4 1.19 OPERAB LE - OPERABI LITY.......................................

1-4 1.20 OPERATIONAL MODE - M0DE......................................

1-4 1.21 PHYSICS TESTS................................................

1-4 1.22 PRESSURE BOUNDARY LEAKAGE....................................

1-4 1.23 PROCESS CONTROL PR0 GRAM......................................

1-4 1.24 PURGE - PURGING..............................................

1-4 1.25 QUADRANT POWER TILT RAT 10....................................

1-5 1.26 RATED THERMAL P0WER..........................................

1-5 1.27 REACTOR TRIP SYSTEM RESPONSE TIME............................

1-5 1.28 REPORTABLE EVENT.............................................

1-5 1.29 SHUTDOWN MARGIN..............................................

1-5 1.30 SITE B00NDARY................................................

1-5

(

1.31 SLAVE RELAY TEST.............................................

1-5 V0GTLE - UNIT 1 I

INDEX

('

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.0 APPLICABILITY...............................................

~3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL Shutdown Margin - MODES 1 and 2..........................

3/4 1-1 Shutdown Margin - MODES 3, 4 and 5.......................

3/4 1-3 FIGURE 3.1-1 REQUIRED SHUTDOWN M"RGIN FOR MODES 3 AND 4 (MODE. 4 WITH AT LEAST ONE AEAC40R-600EAMT-MIMP RUNNING)..

3/4'l-3a It c P FIGURE 3.1-2 REQUIRED SHUTDOWN MARGIN FOR MODE 5 (MODE 4 WITH AT LEAST ONE -RESIDUAL HEAT REMOVAL PUMP RUNNING)............

3/4 1-3b n Hit t

Moderator Temperature Coefficient........................

3/4 1-4 Minimum Temperature for Criticality......................-

3/4 1-6 3/4.1.2 B0 RATION SYSTEMS

[ ~

Flow Path - Shutdown.....................................

3/4 1-7 Flow Paths - Operating...................................

3/4 1-8 Charging Pump - Shutdown.................................

3/4 1-9 Charging Pumps - Operating...............................

3/4 1-10

. Borated Water Source -

Shutdown...........................

'3/4 1-11 Borated Water Sources - Operating........................

3/4 1-12 3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group' Height.............................................

3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE CONTROL OR SHUTDOWN R0D...........

3/4 1-16 i

Position Indication Systems - Operating..................

3/4 1-17 j

Position Indication System -

Shutdown....................

3/4 1-18 Rod Drop Time............................................

3/4 1-19 Shutdown Rod Insertion Limit...................

3/4 1-20 Control Rod Insertion Limits.............................

3/4 1-21 i

FIGURE 3.1-3 R0D BANK INSERTION LIMITS VERSUS THERMAL POWER.......

3/4 1-22 l

i l

V0GTLE - UNIT 1 IV l

INDEX f

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS L

r l

PAGE SECTION 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE....................................

3/4 2-1 FIGURE 3.2-1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL P0WER......................................

3/4 2-3 3/4.2.2 HEAT FLUX H0T CHANNEL FACTOR.7..F.d....................

3/4 2-4 FIGURE 3.2-2 K(Z) - NORMALIZED F (Z) AS A FUNCTION OF CORE HEIGHT.

3/4 2-5 q

NUCLEARENTHALPYRISEHOTCHANNELFACTOR-Fh...........

3/4 2-8 3/4.2.3 3/4.2.4 QUADRANT POWER TILT RATI0................................

3/4 2-10 3/4.2.5 DNB PARAMETERS...........................................

3/4 2-13 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION......................

3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION...................

3/4 3-2 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE C

REQUIREMENTS.............................................

3/4 3-9 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION........................................

3/4 3-15 TABLE 3.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION..........................................

3/4 3-17 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETP0INTS...........................

3/4 3-28 TABL'E 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS..........:.....

3/4 3-36 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring For Plant Operations................

3/4 3-45 TABLE 3.3-4 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS.....................................

3/4 3-46 TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS.....................

3/4 3-48 Movable Incore Detectors.................................

3/4 3-49 Seismic Instrumentation..................................

3/4 3-50 V0GTLE - UNIT 1 V

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

{

SECTION PAGE TABLE 3.3-5 SEISMIC MONITORING INSTRUMENTATION....................

3/4 3-51 TABLE 4.3-4 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................................

3/4 3-52' Meteorological Instrumentation...........................

3/4'3-53 TABLE 3.3-6 METEOROLOGICAL MONITORING INSTRUMENTATION.............

3/4 3-54 Remote Shutdown System...................................

3/4 3-55 TABLE 3.3-7 REMOTE SHUTDOWN SYSTEM MONITORING INSTRUMENTATION.....

3/4 3-56 Accident Monitoring Instrumentation......................

3/4 3-58 TABLE 3.3-8 ACCIDENT MONITORING INSTRUMENTATION...................

3/4 3-59 Chlorine Detection Systems..............................

3/4 3-63 Loose-Part$ Detection System (Deleted)..................

3/4 3-64 k Radioactive Liquid Effluent Monitoring Instrumentatio'n...

3/4 3-65 TABLE 3.3-9 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3/4 3-66 TABLE 4.3-5 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-68

(

Radioactive Gaseous Effluent Monitoring Instrumentation..

3/4 3-71 TABLE 3.3-10 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION..........................................

3/4 3,72 TABLE 4.3-6 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................

3/4 3-76 l

High-Energy Line Break Isolation Sensors.................

3/4 3-79 TABLE 3.3-11 'HIGH-ENERGY LINE BREAK INSTRUMENTATION...............

3/4 3-80 j

3/4.3.4 TURBINE OVERSPEED PROTECTION..............................

3/4 3-81 L

V0GTLE - UNIT 1 VI s

/

m m

INDEX b'

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 1

3/4.4.9

. PRESSURE / TEMPERATURE LIMITS p

/ -,

Reactor Coolant 5ystem........................ f.........

3/4 4'20 FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS V l

APPLICABLE UP TO 16 EFPY............................'....

3/4 4-31, FIGURE 3.4-3 REACTOR COOLANT SYSTEM COOLDOWN LIMITATIONS -

APPLICABLE UP TO 16 EFPY.................................

3/4'4-32 s

Pressurizer..............................................

3/4 4-33 Cold Overpressure Protection Systems.....................

'3/4 4-34 FIGURE 3.4-4 $.WSLLOWAB12 NOMINAL PORV SETPOINT FOR THE COLD l

OVERPRESSURE PROTECTION SYSTEM...........................

3/4 4-35 3/4.4.10 STRUCTURAL I NTEG RITY.....................................

3/4 4r37 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.............................

3/4 4-38 s

3/4.5 EMERGENCY CORE COOLING SYSTEMS i

[

3/4.5.1 ACCUMULATORS..................................'...........

3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,yg GREATER THAN OR EQUAL TO 350'F.... 3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg LESS.THAN 350'F ECCS Subsystems..........................................

3/4 5-7 Safety Injection Pumps...................................

3/4 5-9 3/4.5.4 REFUELING WATER STORAGE TANK.............................

3/4 5-10 1

4 V0GTLE - UNIT 1 VIII 1

i

r..

.n i

l INDEX n

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE

.t 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING I

3/4.32;1o MONITORING PR0GFAM.......................................

3/4 12-1 TABLE 3.12.1 RAOIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM........

3/4 12-3 TABLE 3.1'2-I~ REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES.................................

3/4 12-9 TABLE 4.12-1 QETECTION CAPABILITIES F0P ENVIRONMENTAL SAMPLE.

ANALYSIS LOWER LIMIT OF DtTtii. TION (LL0)..............

3/4 12-10 3/4.12.2 LAN D U S E. C E N S 'J S..........................................

3/4 12-13 9

3/4.12.3 INTERLABORATORY COMPARISON PR0 GRAM.......................

3/4 12-14 BASES t

,r i

~.

sectrost 3/4.0 A P P L I C AB I L I Tj(..............................................

B 3/4 0-1 3/4.1 REACTIVITY CONTROL SYSTEMS T

3/4.1.1 BORATION CONTR0L..........................................

B 3/4 1-1 3/4.1.2 BORATION SYSTEMS..........................................

B 3/4 1-2 i.

n i

-i/4.1.3 MOVAB L E CON (RO', AS S EMB LI ES................................

'a 3/4 1-3 g.-

i

?4 N,

i e

I l

V0GTLE - UNIT 1 XIV I

INDEX

(

BASES PAGE SECTION 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RE ACTOR COOLANT LOOPS AND COOLANT CIRCULATION.............

B.3/4 4-1 B 3/4 4-2 3/4.4.2. SAFETY VALVES.............................................

B 3/4 4-2 3/4.4.3 PRESSURIZER...............................................

B 3/4 4-3 3/4.4.4 RELIEF VALVES.............................................

STEAM GENERATORS........................................'..

B'3/4 4-3 3/4.4,5 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE............................

B 3/4 4-4 B 3/4 4-5 3/4.4.7 CHEMISTRY.................................................

3/4.4.8 SPECIFIC ACTIVITY.........................................

B 3/4 4-5

.3/4.4.9 PRESSURE / TEMPERATURE LIMITS...............................

B 3/4 4-7 TABLE B 3/4.4-1 REACTOR VESSEL T0UGHNESS..........................

B 3/4 4-9

{

FIGURE B 3/4.4-1 FAST NEUTRON FLUENCE (E>1MeV) AS A FUNCTION OF FULL POWER SERVICE LIFE..................................

B 3/4 4-10 FIGURE B 3/4.4-2 EFFECT OF FLUENCE AND COPPER CONTENT ON SHIFT OF RT FOR REACTOR VESSELS EXPOSED TO 550'F............

B 3/4 4-11 NOT STRUCTURAL INTEGRITY............... a slAVIM AT rg B 3/4 4-16 3/4.4.10 3/4.4.11 REACTOR COOLANT SYSTEM VENTS.............................

B 3/4 4-16 3/4.5 EMERGENCY CORE COOLING SYSTEMS B 3/4.5-1 3/4.5.1 ACCUMULATORS..............................................

3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS...............................

B 3/4 5-1 3/4.5.4 REFUELING WAT ER STORAGE TANK..............................

B 3/4 5-2 b

V0GTLE - UNIT 1 XVI

INDEX c

BASES PAGE SECTION 3/4.7 PLANT SYSTEMS B 3/4 7-1 3/4.7.1 TURBINE CYCLE.............................................

B 3/4 7-3

'3/4.7.2. STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION...........

B 3/4 7-3 3/4.7.3 COMPONENT COOLING WATER SYSTEM............................

B 3/4 7-3 3/4.7.4 NUCLEAR SERVICE COOLING WATER (NSCW)

SYSTEM...............

B 3/4 7-3 3/4.7.5 U LT I MAT E HE AT S I NK........................................

3/4.7.6 CONTROL ROOM EMERGENCY FILTRATION SYSTEM..................

B 3/4 7-3 3/4,7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST SYSTEM.....

B 3/4 7-4 B 3/4 7-4 3/4.7.8 SNUBBERS..................................................

B 3/4 7-6 3/4.7.9 SEALED SOURCE CONTAMINATION...............................

(

B 3/4 7-6 3/4. 7.10 AREA TEMPERATURE MONITORING...............................

3/4.7.11 ENGINEERWG SAFETY FEATURES (ESF) ROOM COOLER AND B3/47-6l eD SAFETY-RELATED CHILLER SYSTEM.............................

3/4 7.12 REACTOR-COOLANT PUMP THERMAL BARRIER COOLING WATER B 3/4 7-6 IS0LATION.................................................

l 3/4 7.13 DIESEL GENERATOR BUILDING AND AUXILIARY FEEDWATER B 3/4 7-7 PUMPHOUSE ESF HVAC SYSTEMS...............................

3/4.8 ELECTRICAL POWER SYSTEMS l~

3/4.8.2, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, and B 3/4 8-1 ONSITE POWER DISTRIBUTION...............................

l

~

B 3/4 8-3 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES...................

i l

l('

V0GTLE - UNIT 1 XVIII

INDEX BASES SECTION PAGE 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.......................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION...........................................

B 3/4 9-1 3/4.9.3 DECAY TIME................................................

B 3/4 9-1 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS.........................

B 3/4 9-1 3/4.9.5 COMMUNICATIONS............................................

B 3/4 9-1 3/4.9.6 REFUELING MACHINE.........................................

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS...................

B 3/4 9-2 3/4.9.8 RESIDUAL HEAT REMOVAL AND COOLANT CIRCULATION.............

B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION ISDLATION SYSTEM..................

B 3/4 9-3 3/4.9.10 and 3/4.9.11 WATER LEVEL - REACTOR VESSEL and STORAGE P00L............................................

B 3/4 9-3 3/4.9.12FUELHANDLINGBUILDINGPOSTACCIDENTVENTILATIONSYSTEM8.

B 3/4 9-3 i

3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 S.HUTDOWN MARGIN...........................................

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION, AND POWER DISTRIBUTION LIMITS....

B 3/4 10-1 3/4.10.3 PHYSICS TESTS.............................................

B 3/4 10-1

~

3/4.10.4 REACTOR COOLANT L00PS.....................................

B 3/4 10-1.

3/4.10.5 POSITION INDICATION SYSTEM - SHUTD0WN.....................

B 3/4 10-1 V0GTLE - UNIT 1 XIX

--e u.-

+

c

+.

-e.----.

- +. -

INDEX b

ADMINISTRATIVE CONTROLS PAGE SECTION 6-1 6.1 RESPONSIBILITY..............................................

6-1

.6.2 ORGANIZATION................................................

6-1 6.2.1 0FFSITE...................................................

6-1 6.2.2 PLANT 5TAFF...............................................

FIGUPE 6.2-1 0FFSITE ORGANIZATION...............................

6-3 FIGURE 6.2-2 PLANT ORGANIZATION.................................

6-4 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION. F#. #..(W.'T..@.47V6-5 G

'6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

Function..................................................

6-6 j

6-6 Composition............................................

3 6-6

. Responsibilities..........................................

6-6 Records...................................................

-(1 6.2.4 SHIFT TECHNICAL ADVIS0R...................................

6-6 6-6 6.3 TRAINING....................................................

t 6.4 REVIEW AND AUDIT............................................

6-7 1

6.4.1 PLANT REVIEW BOARD (PRB) l 6-7 l

Function..................................................

6-7 Composition...............................................

6-7 l

Alternates................................................

6-7 Meeting Frequency.........................................

6-7 Quorum....................................................

6-7 Responsibilities..........................................

6-9 Records...................................................

l l

l t

l-s

~

V0GTLE - UNIT 1 XXII l

1

4 INDEX ADMINISTRATIVE CONTROLS SECTION 6.4.2 SAFETY REVIEW BOARD (SRB).

Function..................................................

6-9 6-9 Composition...............................................

~

6-10 Alternates................................................

6-10 Consultants...............................................

6-10 Meeting Frequency.........................................

6-10 Quorum....................................................

6-10 Review....................................................

6-11 Audits....................................................

6-12 Records...................................................

6.5 REPORTABLE EVENT ACTI0N.....................................

6-12 e

6.6 SAFETY LIMIT VIOLATION......................................

6-13 i

6.7 PROCEDURES AND PR0 GRAMS.....................................

6-13 6.8 REPORTING REQUIREMENTS 6.8.1 ROUTINE REP 0RTS...........................................

6-16 6-16 Startup Report............................................

6,

An nua l Repo rts......................... [. /a.................

S rves nce Annual Radiological Environmental,_p;;r:Jr; Report........

6-17 r

Semiannual Radioactive Effluent Release Report............

6-18 6-20.k Monthly Operating Report$.................................

6-20 f

Radial Peaking Factor Limit Report........................

6-20

'6.8.2 SPECIAL REP 0RTS...........................................

6-21 6.9 RECORD RETENTION............................................

i l

l l k t

i V0GTLE - UNIT 1 XXIII l

l l

'gh+y----N-m--m------T

--M g-y b-

+y.v-gm-ww y-

-ryr.s+i--4-----m-m-ewyg-w&r-.w--r~--

,--w-

---w--y--------w-w 37-.w-wyy ym-y-yv---

w, vm m gr-yy

~

INSTRUMENTATION l

CHLORINE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.3.3.7 Two independent Chlorine Detection Systems (A-12110, A-12112), with

{

their Alarm / Trip Setpoints adjusted to actuate at a chlorine concentration of less than or equal to 2 ppm, shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, 4, 5* and 6*, if chlorine gas is stored onsite in quantities greater than 20 lb.

ACTION:

a.

With one Chlorine Detection System inoperable, restore the inoperable system to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of the Control Room Emergency Ventilation System in the isolation mode of operation.

With both Chlorine Detection Systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months b.

initiate and maintain operation of the Control Room Emergency Ventilation System in the isolation mode of operation.

c.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE ~ REQUIREMENTS 4.3.3.7 EachChlorineDetectionSystem(A-12110,A-12112)shall'bedemonstrated OPERABLE by performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an ANALOG CHANNEL OPERATIONAL TEST at least once per 31 days and a CHANNEL CALIBRATION at least once per 18 months.

l l

l l.

i l

l k

During movement of irradiated fuel or movement of loads over irradiated fuel.

V0GTLE - UNIT 1 3/4 3-63 i

-=

INSTRUMENTATION

' (

HI'GH-ENERGY LINE BREAK ISOLATION SENSORS I

l LIMITING CONDITION FOR OPERATION 3.3.3.11 The high energy line break instrumentation listed in Table 3.3-11 shall be OPERABLE.

- APPLICABILITY: As noted in Table 3.3-11.

ACTION:

a.

With the number of OPERABLE electric steam boiler isolation instruments less than the Minimum Channels OPERABLE as required by Table 3.3-11, re-store the inoperable instruments to 0PERABLE status within 7 days or sus-pend operation of the electric steam boiler until the inoperable sensors are restored to OPERABLE status.

The provisions of Specification 3.0.4 are not applicable.

b.

With the number of OPERABLE steam generator blowdown line isolation instru-ments or letdown line isolation instruments less than the Minimum Channels OPERABLE as required by Table 3.3.11, restore the inoperable instruments to OPERABLE status within 7 days or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

C SURVEILLANCE REQUIREMENTS 4.3.3.11 Each of the above high energy line break isolation instruments shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL TEST at least once per 18 montns.

l l

\\

L V0GTLE -' UNIT 1 3/4 3-79 4

--,--.,--.,..,,,_..,_m_.-

._,.~,,_,--,.,,_-.,,,-,.,_,,-__-..__---_,----.,--,..,,.,,,,..,...,,,,mm..,_.-,.----,_,,.r-_,~,,w--

I 250 -

T.

t UNACCEPTABLE OPERATION y

9 u.

O W

b 150 i b

z 5

8

^

o>

k3 100 E

9 I

Z ACCEPTABLE OPERATION 50 2

8w E

8 l

l 0

20 30 40 50 60 70 80 90-100 PERCENT OF RATED THERMAL POWER FIGURE 3.4-1

$FAC 70A.

DOSE EQUIVALENT I-131 ""."""" COOLANT SPECIFIC ACTIVITY LIMIT VERSUS ACTIVITY >l pCi/ gram DOSE EQUIVALENT I-131 [?'"' C0dLA PERCENT OF RATED THERMAL POWER WITH THE JR!"

l.

A K4C70A k

l V0GTLE - UNIT 1 3/4 4-26

~~^

~~

TABLE 4.4-4 g

REACTOR COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM r-7 TYPE OF MEASUREMENT SAMPLE AND ANALYSIS

. MODES IN WHICH SAMPLE AND ANALYSIS FREQUENCY AND ANALYSIS REQUIRED c

h 1.

Gross Radioactivity At least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

1,2,3,4 Determination

y 2.

Isotopic Analysis for DOSE EQUIVA'-

1 per 14 days.

1 LENT I-131 Concentration 3.

Radiochemica etermination**

1 per 6 months ***

1 4.

Isotopic Analysis for Iodine a) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 1#, 2#, 3#, 4#, 5#

Including I-131, I-133, and I-135 whenever the specific activity exceeds 1 pCi/ gram DOSE EQUIVALENT I-131 2

y or 100 6 pCi/ gram of gross radioactivity, and

[

b) One sample between 2 1,2,3 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months following e

i a THERMAL POWER change exceeding 15%

i of the RATED THERMAL POWER within a 1-hour period.

i i

l I

i l

3000 CURVE APPLICABLE FOR THE SERVICE PERIOD UP TO 16 EFPY

(

.G RT Af ter 16 EFPY NDT w

LE AK TEST a.1/4 T = 1100 F

b. 3/4T = 870'F L1 IT CRITICALITY h

LIMIT 0

FOR 60 /HR g 2000 UNACCEPTABLE HEATUP OPERATION e

z CRITICALITY 2

LIMIT g

0 FOR 100 /HR o

HEATUP g

I t;

5 600 F/HR HEATUP BASED ON INSERVICE -

%. 1000 g

CUWE [

HYDROSTATIC TEST 0

5 TEMPER ATURE (255 F)

(

E F

FOR T HE SERVICE PERIOD UP TO 16 EFPY i

0 100 F/HR HEATUP ACCEPTABLE CURVE OPERATION 1

0.0 0.0

-100 200 300 400 500 INDICATED TEMPER ATURE (OF)

MATERIAL BASIS -

c

.c....

io n.

A(. a*

Mt l

a%o,'~.- ag g, i

..,........ p,,,,p.

FIGURE 3.4-2 REACTOR COOLANT SYSTEM HEATUP LIMITATIONS APPLICABLE UP TO 16 EFPY l

l l

l V0GTLE - UNIT 1 3/4 4-31 1

i l

l

PLANT SYSTEMS 3/4.7.7 PIPING PENETRATION AREA FILTRATION AND EXHAUST 575 TEM I

SURVEILLANCE REQUIREMENTS (continued) 2)

Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Section 13 of ANSI N510-1980 meets the laboratory testing cri-terion of greater than or equal to 99.8% when tested with methyl' iodide at 30*C and 70% relative humidity.

3)

Verifying a system flow rate of 13,600 cfm + 20%, -0% during system operation when tested in accordance with Section 8 of ANSI N510-1980.

t c.

After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation, by verifying, within 31 days after removal, that a laboratory analysis of a repre-

{

sentative carbon sample obtained in accordance with Section 13 of ANSI N510-1980 meets the laboratory testing criteria of greater than or equal to 99.8% when tested with methyl iodide at 30*C and 70%

relative humidity; d.

At.least once per 18 months by:

1)

Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 6 inches I

Water Gauge while operating the system at a flow rate of i

13,600 cfm + 20%, -0%.

2)

Verifying that the system starts on a Containment Ventilation Isolation test signal, 3)

Verifying that the system maintains the Piping Penetration Fil-tration Exhaust Unit Room at a negative pressure of greater than or equal to 1/4 inch Water Gauge relative to the outside atmosphere (PDIC-2550, PDIC-2551), and 4)

Verifying that the heaters dicsipate 80 1 4 kW when tested in accordance with Section 14 of ANSI N510-1980.

e.

After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove greater than or equal to 99.95% of the DOP when they are tested in place in accordance with Section 10 of ANSI N510-1980 while. operating the system at a flow rate of 13,600 cfm + 20%, -0%.,

f.

After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove greater than or equal to 99.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with Section 12 of ANSI N510-1980 while operating the system at a flow rate of 13,600 cfm + 20%, -0%.

V0GTLE - UNIT 1 3/4 7-18 i

's 9

10 9

1 8

/

REJECT

/

J

/.+

C c

/

~

4 CONTINUE TESTING

/

db?

I Q

/

ACCEPT

/

1 0

10 20 30 40 50 60 70 80 90 100 N

FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST t

V0GTLE - UNIT 1 3/4 7-24

ELECTRICAL POWER SYSTEMS

SURVEILLANCE REQUIREMENTS (Continued) p 2)

Verifying the generator is synchonized, loaded to an indicated

~

-value of 6100 - 7000 kW*** in less than or equal to 60 seconds, and operates with a load of 6800-7000 kW*** for at least 60 minutes.

-This test, if it is performed so it coincides with the testing required by Surveillance Requirement 4.8.1.1.2.a.5, may also serve to concurrently meet those requirements as well.

h-

.At'least once per 18 months,** during shJtdoWD, by:

1)

Subjecting the diesel to an inspection in accordance with proce-dures prepared in conjunction with its manufacturers' recommenda-tions for this class of standby service; 2)

Verifying the diesel generator capability to reject a load of

~

greater thare or equal to 671 kW (motor-driven auxiliary feedwater-pump) while maintaining voltage at 4160 + 240, -410 volts'and speed of less than 484 rpm (less than nominal speed plus 75%

of the difference between nominal speed and the Overspeed Trip Setpoint); and recovering voltage to within 4160 + 170)-410 volts.

within 3 seconds.

3)

Verifying the diesel generator capability to reject a load of 7000 kW without tripping.

The generator voltage shall not exceed 5000 volts during and following the load rejection;

'4)

Simulating a loss-of-offsite power by itself, and:

C-a)

Verifying deenergization of the emergency busses and load shedding from the emergency busses, and b)

Verifying the diesel starts on the auto-start signal, i

energizes the emergency busses with permanently connected loads within 11.5 seconds,* energizes the auto-connected shutdown loads through the load sequencer and operates for greater than or equal to 5 minutes while its generator is loaded with the shutdown loads. After energization, the steady-state voltage and frequency of the emergency busses shall be maintained at 4160 +170, -410 volts and 60 1 1.2 Hz 4

i-during this test.

5)

VerifyingthatonanESFActuationtestsignal,without' loss-of-offsite power, the diesel generator starts on the-auto-start j

signal and operates on standby for greater than or equal'to 5 minutes.

The generator voltage and 'requency shall be 4160

+170, -410 volts and 60 1 1.2 Hz within 11.4 seconds after the

All engine starts for the purpose of surveillance testing as required by Specification 4.8.1.1.2 may be preceded by an engine prelube period as recom-mended by the manufacturer to minimize mechanical stress and wear on the diesel engine, i

- For any start of a diesel, the diesel must be operated with a load in accor-dance with the manufacturer's recommendations.

!(

- - This band is meant as guidance to avoid routine overloading of the engine.

l Loads in excess of this band or momentary variations due to changing bus i

loads shall not invalidate this test.

V0GTLE - UNIT 1 3/4 8-6

r O

O S

l;;-

h 400 i

i i

i i i i

i i i iii i

i i

i i i i

i i i i Upper umit i

M 0.30% COPPER SASE.O.M% WELD I

d N

0.25% COPPE R 9ASE.O.20% WE LD a

200 l

,i Lower Limit a~

100 g

o Z

80 p

s c

d

)

9 60 0.20% COPPE R SASE. 0.15% WELO p

0.15% COPPE R BASE 0.10% WE'.O 0.10% COPPE R SASE. 0.05% WE LD 40 i

i l

i I I I i

l I i i11 I

I i

i i

i 1 20 18 20 10 2

4 6

8 10 2

4 6

8 10 2

j FAST NEUTROM FLUENCE (N/CM, E >l MeV) 4 FIGURE B 3/4.4-2

)

EFFECT OF FLUENCE AND COPPER CONTENT ON SHIFT OF RTET FOR REACTOR VESSELS EXPOSED TO 550*F AAo#47/d# 47

REACTOR COOLANT SYSTEM 3/4.4.4 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.4 All power-operated relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

ACTION:

f a.

With one or more PORV(s) inoperable, because of excessive seat leakage, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s); otherwise, be in at least l-HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the i

following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one or more PORV(s) inoperable due to causes other than exces-sive seat leakage, within I hour either restore the PORV(s) to OPERABLE status or close the associated block valve (s) and remove power from the block valve, and 1.

With only one PORV OPERABLE, restore at least a total of two

. C-PORVs to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , or 2.

With no PORVs OPERABLE, restore at least one PORV to OPERABLE status within I hour or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (1) restore the block valve (s) to OPERABLE status or close the block valve (s) and remove power from the block valve (s) or close the PORV and remove power from its associated solenoid valve; and (2) apply ACTION b above, as

{

appropriate, for the isolated PORV(s).

d.

The provisions of Specification 3.0.4 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.4.4.1 Each PORV shall be demonstrated OPERABLE at least once per 18 months by:

r a.

Operating the valve through one complete cycle of full travel, and b.

Performing a CHANNEL CALIBRATION.

F k

l

'/ 'j f L.i. U$*("k Y $ $ f f $ *F' ?

b Y"Y Y '

~

,. 7.,,.. T

"'1 I

V0GTLE - UNIT 1 3/4 4-10 i

PLANT SYSTEMS

[

AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION i

3. 7.1. 2 At least three independent steam generator auxiliary feedwater

' pumps and associated flow paths shall be OPERABLE with:

a.

Two motor-driven auxiliary feedwater pumps, each capable of being powered from separate emergency busses, and b.

One steam turbine-driven auxiliary feedwater pump capable of being powered from an OPERABLE steam supply system.'

APPLICABILITY:. MODES 1, 2, and 3.

. ACTION:

a.

With one auxiliary feedwater pump inoperable restore the required s

auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With two auxiliary feedwater pumps inoperable, be in at least HOT STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With three auxiliary feedwater pumps inoperable, immediately initiate corrective action to restore at least one auxiliary feedwater pump to OPERABLE status as soon as possible.

SURVEILLANCE REQUIREMENTS 4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1)

Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1605 psig at a flow of greater than or equal to 175 gpa (FI-15101, FI-15102);

2)

Verifying that the steam turbine-driven pump develops a dis-charge pressure of greater than or equel to 1675 psig at a flow of greater than or equal to 145 gpm (FI-5100) when the secondary steam supply pressure (PI-5105A, PI-51058) is greater than 900 psig.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

m.,,/.,. 3., U...' 5T N Y.

[ N / F "r""7 / C/t N T'/'i/ IFt/ O ?}#I 9 II ;;/'YiY t Y I" D i d 4#

1

(

V0GTLE - UNIT 1 3/4 7-4

h PLANT SYSTEMS

[

MAIN STEAM LINE ISOLATION VALVES

-LIMITING CONDITION FOR OPERATION 3.7.1.5 Two main steam line isolation systems (each system consisting of.a main steam isolation valve (MSIV) and its associated bypass valve (MSIBV)).per i

steam line shall be OPERABLE.*

f APPLICABILITY: MODES 1, 2, and 3 ACTION:

MODE,1:

a.

With two main steam line isolation systems in any one steam line inoperable; POWER OPERATION may continue provided each MSIV in the affected steam line is open and at least one main steam line isola-tion system in the affected steam line is restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; 'otherwise reduce power to less than or equal to 5% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

~

b.

With one main steam line isolation system inoperable, power opera-tion may continue provided the MSIV in the affected isolation system is open and the inoperable system is restored to OPERABLE status within 3 days.

Othemise, reduce power to less than or equal to 5% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

MODES 2 and 3:

a.

With two main steam line isolation systems in any one steam line C

inoperable, subsequent operation in MODES 2 or 3 may proceed provided at least one main steam line isolation system in the affected steam line is maintained closed.

The provisions of Specification 3.0.4 are not applicable. Otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With one main steam line isolation system inoperable but closed, subsequent operation in MO, DES 2 or 3 may proceed provided that.the isolation system in the affected steam line is maintained closed.

The provisions of Specification 3.0.4 are not applicable.

c.

With one main steam line isolation system inoperable but open, either close the OPERABLE isolation system or restore the inoperable system to OPERABLE status within 7 days.

Otherwise be in H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in H0T SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.1.5 Each MSIV and MSIBV shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.

The provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

"An OPERABLE main steam line isolation system can consist of an OPERABLE MSIV and an inoperable associated MSIBV provided the inoperable MSIBV is maintained closed.

.--t4, u 2 *n ' n w L-mava ~ u s--

ce. w 2, W,..

/-L+

18E,7 MM /'2Z..H T /. 71C' E'- [MUlG7 d I"I 'O"U.','A /*"e N,4_ Wz ax!.iT,- m'=7'm'"'I '

'"'""""V'~"'

V

..r -

rrr--

V0GTLE - UNIT 1 3/4 7-9

~...

i 3/4.9 REFUELING OPERATIONS

['

3/4.9.1 BORON CONCENTRATION d

LIMITING CONDITION FOR OPERATION 3.9.1 The boron concentration of all filled portions of the Reactor Coolant

~ System and the refueling canal shall be maintained uniform and' sufficient to ensure that the more restrictive of the following' reactivity conditions are met:

A K,7f of 0.95 or less, or a.

l b.

A boron concentration of greater than or equal to 2000 ppm.

Additionally, valves 1208-U4-175, 1208-U4-177, 1208-U4-183, and 1208-U4-176 shall be closed and secured in position.

APPLICABILITY: MODE 6.

L ACTION:

With the requirements of a. and b. above not satisfied, immediately a.

suspend all operations involving CORE ALTERATIONS or positive 4

reactivity changes and initiate and continue boration at greater than i

l[.

or equal to 30 gpm of a solution containing greater than or equal to

'L 7000 ppm. boron or its equivalent until K,gf is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2000 ppm, whichever is the more restrictive.

b.

With valves 1208-U4-175, 1208-U4-177, 1208-04-183, and 1208-U4-176 not closed and secured in position, immediately close and secure in position.

SURVEILLANCE REQUIREMENTS 4.9.1.1 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once per 72. hours.

~.9.1.2 Valves 1208-U4-175, 1208-U4-177, 1208-U4-183, and 1208-U4-176 shall be 4

verified closed and secured in position by mechanical stops at least once per 31 days.

1 "Du ing itial el lo

, the bor n con ntratio limit ion rt r u ing c al s not a licab provide the r fueling anal vel ver fi be

(

elow the rea or ve sel flan elev ion at ast ce pe 12 ur.

(

V0GTLE - UNIT 1 3/4 9-1

]

r TABLE 3.3-8 (Continued)

E ACCIDENT MONITORING INSTRUMENTATION TOTAL MINIMUM.

[

NO. OF CHANNELS z

INSTRUMENT CHANNELS OPERABLE

' ACTION w

w

12. Condensate Storage Tank Level-2/ tank

~1/ tank 31 (Loop 5101, 5111, 5104 & 5116)

13. Auxiliary Feedwater Flow 2/ feed line 1/ feed line 31 (Loop 5152, 15152, 5153, 15153, 5151, 15151, 5150 & 15150) 14.

Containment Radiation Level Range) 2 1

33 (Loop 0005 & 0006) 15.

Steamline Radiation Monitor 1/sta. line 1/sta. line 33 (Loop 13119, 13120, 13121 & 13122)

,s

~

4/ quad / train 2/ quad / train 30

16. Core Exit Thermocouples E

17.

Reactor Coolant System Subcooling 2

1 31

18. Neutron Flux (Extended Range) 2 1

31 (Loop 13135A & 131358) 19.

RVLIS 2

1 34 20.

Containment Hydrogen Concentration 2

1 31 (Loop 12979 & 12980) 21.

Containment Pressure (Extended Range) 2 1

31-(Loop 10942 & 10943) 22.

Containment Isolation Valve Position Indication

1/ valve 1/ valve 36

" Applicable for containment isolation valve position indication designated as post-accident monitoring instru-mentation (containment isolation valves which receive containment isolation Phase A.or containment ventilation isolation signals).

TABLE 3.3-10 RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION MINIMUM CHANNELS OPERABLE APPLICABILITY ACTION INSTRUMENT e

b 1.

GASEOUS WASTE PROCESSING SYSTEM w

Noble Gas Activity Monitor -

a.

Providing Alarm and Automatic 45 Termination of Release (ARE-0014) 1 b.

Effluent System Flow Rate 46 1

Measuring Device (AFT-0014) 2.

GASEOUS WASTE PROCESSING SYSTEM Explosive Gas Monitoring System R

1/recombiner SO a.

Hydrogen Monitor Y

2/recombiner 49 d

b.

Oxygen Monitor 3.

Condenser Air Ejector and Steam Packing Exhauster System 47 1

Noble Gas Activity Monitor a.

(RE-12839C)

S1 1

b.

Iodine Sampler (RE-128398)

S1 1

c.

Particulate Sampler (RE-12839A) 46 1

d.

Flow Rate Monitor (FT-12839),

(FIS-12862) 46 1

Sampler Flow Rate Monitor I

e.

(FI-4283ST f5a//

V

j TABLE 4.3-6 h

RADI0 ACTIVE GASEOUS EFFLUENT. MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS 1

m ANALOG g

CHANNEL MODES FOR WHICH q

CHANNEL SOURCE CHANNEL OPERATIONAL SURVEILLANCE INSTRUMENT CHECK CHECK CALIBRATION TEST IS REQUIRED g

1.

GASEOUS WASTE PROCESSING SYSTEM

a. Noble Gas Activity Monitor -

Providing Alarm and Automatic i

Termination of Release (ARE-0014) P P

R(3)

Q(1) c

b. Effluent System Flow Rate P

N.A.

R N.A.

c Measuring Device (AFT-0014) y 2.

GASEOUS WASTE PROCESSING SYSTEM Explosive Gas Monitoring System

a. Hydrogen Monitors D

N.A.

Q(4)

M b

]

b. Oxygen Monitors D

N.A.

Q(5)

M b

l 3.

Condenser Air Ejector and Steam j

Packing Exhauster System

a. Noble Gas Activity Monitor D

M R(3)

Q(2) c (RE-12839C) j

b. Iodine Sampler W(6)

N.A.

c (RE-128398) l

c. Particulate Sampler W(6)

N.A.

c (RE-12839A)

d. Flow Rate Monitor D

N.A.

R N.A.

c (FT-12839)

)

e. Sampler Flow Rate Monitor D

N.A.

R Q

c j

(FI-M8 W

/JA//

l U

8'

REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION 3.4.9.2 The pressurizer temperature (TI-0453, TI-0454) shall be limited to:

a.

A maximum heatup of 100*F in any 1-hour period, b.

A maximum cooldown of 200*F in any 1-hour period, and Amaximumauxiliarysp(raywatertemperaturedifferentialof625*F f

c.

(TI-0451 TI-Oi52,.

77-o/M)

APPLICABILITY:

At all times.

ACTION:

With the pressurizer temperature limits in excess of any of the above limits, restore t.e temperature to within the limits within 30 minutes; perform an h

engineering evaluation to determine the effects of the out-of-limit condition on the structural. integrity of the pressurizer; determine that the pressurizer remains acceptable for continued operation or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce the pressurizer pressure to less than 500 psig within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l SURVEILLANCE REQUIREMENTS l

4.4.9.2 The pressurizer temperatures shall be determined to be within the limits at least once per 30 minutes during system heatup or cooldown.

The spray water temperature differential shall be determined to be within the limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during auxiliary spray operation.

i V0GTLE - UNIT 1 3/4 4-33 1

PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2 The. temperatures of both the reactor (TI-0413B, TI-0423B, TI-0433B, TI-0443B) and secondary (TI-1175, TI-1176, TI-1177, TI-1178) coolants in the steam generators shall be greater than 70 F when the pressure, (PI-0408, PI-0418, PI-0428, PI-0438, PI-0514A, PI-0524A, PI-0534A, PI-0544A) of either coolant in the steam generator is greater than 200 psig.

APPLICABILITY:

At all times.

ACTION:

With the requirements of the above specification not satisfied:

a.

Reduce the steam generator pressure of the applicable side to less than or equal to 200 psig within 30 minutes, and b.

Perform an engineering evaluation to determine the effect of the overpressurization on the structural integrity of the steam generator. Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200*F.

SURVEILLANCEREQUIREMENTS 4.7.2 The pressure in each side'of the steam generator shall be determined to be less' than 200 psig at least once per hour when the temperature of either the reactor colant is less than 70'F -(TI-04130, TI-0420",

T!-04339, f.or secondary d TI-04400).-o-( 77-H75) rr-H76, TI-H77, TI-M7h (rr-op38, 7 r-os138, TI-0Y338, TT-0YV3 6 )

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ELECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) on the time of the initial loss of the remaining inoperable offsite a.c. circuit.

A successful test (s) of diesel OPERABILITY per Surveil-lance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 performed under this Action Statement for the OPERABLE diesels satisfies the diesel generator test requirement for Action Statement a.

f.

With two of the above required diesel generators inoperable, demonstrate the OPERABILITY of two offsite A.C. circuits by performing the require-ments of Specification 4.8.1.1.1.a. within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least H0T STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

Following restoration of one diesel generator unit, follow Action Statement b with the time requirement of that Action Statement based on the time of initial loss of the remaining inoperable diesel generator.

A successful test of diesel 0PERA81LITY per Surveillance Requirements 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5 performed under this Action Statement for a restored to OPERABLE diesel satisfies the diesel generator test requirements of Action Statement b.

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the Onsite Class 1E Distribution System shall be:

a.

Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, and indicated power availability.

l 4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:

In accordance with Jte, frequency specified in Table 4.8-1 M a.

(STAGGEREDTESTBASIf>y:

1)

Verifying the fuel level in the day tank (LI-9018, LI-9019),

2)

Verifying the fuel level in the fuel storage tank (LI-9024, LI-9025),

3)

Verifying the fuel transfer pump starts and transfers fuel from the storage system to the day tank, 4)

Verifying the diesel starts and that the generator voltage and frequency are 4160 + 170, -410 volts and 60 + 1.2 Hz within 11.4 seconds

after the start signal. The dTesel generator shall be started for this test by using one of the following signals:

All diesel generator starts for the purpose of surveillance testing as required by Specification 4.8.1.1.2 may be preceded by an engine prelube period as recommended by the manufacturer so that the mechanical stress and wear on the diesel engine is minimized, l

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l l

TABLE 3.3-2 (Continued)

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION b

MINIMUM NMNW l

)

TOTAL NO.

CHANNELS CHANNELS APPLICABLE i

5 F0MCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION-t..

10. Control Room Ventilation Emergency

~

+

i ;.

Mode Actuation a.

Manual Initiation 2

1 1

1,2,3,4, d

5*, 6' 26

}~

b.

Automatic Actuation Logic j

and Actuation Relays 2

1 2

1,2,3,4, d

I 5', 6' 26 1

c.

Safety Injection See Functional Unit 1 above for all Safety Injection l

i initiating functions and requirements.

R d.

Intake Radiogas Monitor 2

1 2-1,2,3,4, d

4 (RE-12116,RE-12117) 5',6' 26 l

11. Fuel Handling Su11 ding Post j

Accident Ventilation Actuation j

,y #

a.

Manual Initiation 2

1 1

1

)

I l

b.

Fuel Handling Building 4

1 1

i g JG Exhaust Duct Radiation Signal (ARE-2532 A&8 i

ARE-2533 A&B) 1

[.$

c.

Automatic Actuation Logic 4

1 1

i and Actuation Relays i

4 e

4 1

TABLE 3.3-2 (Continued)

TABLE NOTATIONS a Trip function may be blocked-in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

Trip function automatically blocked above P-11 and may b'e blocked below' b

P-11 when Safety Injection on low steam line pressure is not blocked.

~During movement of irradiated fuel or movement of loads over irradiated c

fuel within containment.

d The provisions of Specification 3.0.4 are not applicable.

During movement of irradiated fuel or movement of loads over irradiated fuel, e

f Not applicable if one main steam isolation valve and associated bypass iso--

lation valve per steamline is closed.

Containment Ventilation Radiation (RE-2565) is treated as one channel and is g

considered OPERABLE if the particulate (RE-2565A) and iodine monitors (RE-25658) are OPERABLE or the noble gas monitor (RE-2565C) is OPERABLE.

h Manual initiation of Auxiliary Feedwater is accomplished via the pump handswitches.

C^

i Whenever irradiated fuel is in the storage pool, e

ctks Fo ct' ions sociated ith ino rable instr tat foil ett ied in S cificati 3.9.12.

j ACTION STATEMENTS ACTION 14 - With the' number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped' condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 16 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9 (Mode 6).

L V0GTLE - UNIT 1 3/4 3-25

p}.

TABLE 3.3-2 (Continued)

ACTION STATEMENTS (Continued)-

ACTION 24 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or-declare the associated valve ~ inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 25 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STAND 8Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up tc 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

V ACTION 26 - With the number of OPERABLE channels one less.than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

initiate and maintain operation of the Control Room Emergency

{VentilationSystemintheEmergencymode.

With two channels inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of r

theControlRoomEmergencyVentilationSystemintheEmergeny 5 s ACTION 27 - With the number of channels OPERA 8LE one less than the Minimum Channels OPERABLE requirement, restore the number of OPERA 8LE.

channels to the Minimum Channel OPERA 8LE requirement within 7 days, or be in at least HOT STAN08Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in at least HOT SHUTDOWN within the following 6 hcurs, and in COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 28 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, operation may proceed until the performance of the next required TRIP ACTUATING DEVICE OPERATIONAL TEST.

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L V0GTLE - UNIT 1 3/4 3-27

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