ML20149G226
| ML20149G226 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/07/1994 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20149G221 | List: |
| References | |
| 2252, NUDOCS 9410170210 | |
| Download: ML20149G226 (14) | |
Text
.
Docket Number 50-346 License Number NPF-3 Serial Number 2252
- E:r#PLtcABILITY TH,S PABE PROVIDE.D SURVEILLANCE REQUIREMENTS
!4.0.1 Surveillance Requirements snall be applicable during the OPERATIONAL
- . MODES or other conditions specified for individual Limiting Conditions foF l Operation unless otherwise stated in an individual Surveillance Requirement.
l"4.0.2 Each Surveillance Reovirement shall be perfonned within the scocified
- 3. time interval with a maximum allowanle extension not to exceed 25 percent of I
the scecified surveillance interval.
4.0.3 Failure to perform a Surveillance Requirement within the allowed surveil-i lance interval, defined by Specification 4.0.2. shall constitute noncompliance with the OPERA 81LITY requirements for a Limiting Condition for Operation.
)
The time limits of the ACTION requirements are applicable at the time it is ident1fied that a Surveillance Requirement has, not been perfonned.
The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to permit the comple-
,! tien of the surveillance when the allowable (equipment inoperability) outaga time limits of the ACTION requirements are less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
' Surveillance requirements do not have to be performed on inoperatie equipment.
4.0.4 Entry into an OPERATIONAL MODE or other specified appitcabtitty condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been perfonsed within the stated surveil-lance interval or as otherwise specified.
4.0.5 Surveillance Requirements for inservice inspection and tasting of ASME Code Class 1. 2 and 3 components shall be applicable as follows:
a.
During the time period:
1.
From issuance of the facility Operating License to the start of facility consercial operation.. inservice testing of ASME Code Class 1. 2 and 3 pumps and valves shall be performed in accord-
)
ance with Section XI of the ASM Boiler and Pressure Vessel Code 1974 Edition, and Addenda through Summer 1975, except where i
specific writtaa relief has been granted by the Consission.
2.
Following start of facility commercial operation. inservice inspection of ASE Code Class 1. 2 and 3 caponents and inservice testing of ASE Code Class.1. 2 and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addende as reovired by 10 CFR 50. Section 50.55a(g), except where specific writtere relief has been granted by the Conssission pursuant to 10 CFR 50.
Section 50.SSa(g)(6)(1).
3.
furve111ance intervals scecified in Section XI of the ASME Boiler and Pressure Yessel Code and applicable Addenda for the inservice inspec-tion and testing activities required by the ASME Boiler and Pressure Vessel Code and acclicable Addenda shall be applicable as follows in these Technical Scecifications:
- ':AvtS-BESSE. UNIT 1 3/4 0-2 Amenc=ent No. 77,J Aa,145 942017021o 941007 DR ADOCK 05000346 PDR
Docket Number 50-346 License Number NPF-3 Serial Number 2252 Attachment THIS PAGE PROVIDED
~
APPLICABILITY SURVEILLANCE REQUIREMENTS (Continued)
ASME Boiler and Pressure Vessel Code and applicable Required frequencies Addenda terminology for for perfonning inservice inservice inspection and inspection and testing testing criteria activities At least once per 7 days Weekly Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Yearly or annually At least once per 366 days The provisions of Specification 4.0.2 are applicable to the c.
above required frequencies for performing inservice inspec-tion and testing activities.
Perfordance of the above inservice inspection and testing d.
activities shall be in addition to other specified Surveillange Requirements.
Nothing in the ASME Boiler and Pressure Vessel Code shall be e.
construed to supersede the~ requirements of any Technical Specification.
DAVIS-BESSE, Ur1IT 1 3/4 0-3
Docket' Number 50-346 License Number NPF-3 Serial Number 2252 At tachmerit -
Page 8 EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - T.,.
A280'F l.
LIMITING CONDITION FOR OPERATION 3.5.2 Two independent ECCS subsystems shall be OPERABLE with each subsystem comprised of:
a.
One OPERABLE high pressure irtjection (HPI) pump, b.
One OPERABLE low pressure injection (LPI) pump, c.
One OPERABLE decay heat cooler, and
'd.
An' OPERABLE flow path capable of taking suction from the borated water storage tank (BWST) on a safety injection signal and manually transferring suction to the containment sump during the recirculation phase of operation.
APPLICABILITY: MODES 1. 2 and 3.
ACTION:
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
I b.
In the event the ECCS is actuated and injects water into the
~
Reactor Coolant System, a Special Repoct shall be prepared and submitted to the Comission pursuant'to Specification 6.9.2 within 90 days describing the circumstances of the actuation
.I and the total accumulated actuation cycles to date.
SURVEILLANCE REOUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
At least once per 31 days by verifying that each valve (manugl.
a.
power operated or automatic) in the flow path that is not locked, sealed or otherwise secured in position is in its correct position.
DAVIS-BESSE, UNIT 1 3/4 5-3 Amendment No. M 182 i
- U U 5.,)c,se.)g b h. lO.%e o Y
h 4
up
, cama 1v: v d,
av i
Docket. Number 50-346 License Number NPF-3 Serial Number 2252
{
Attachment Page 9 SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 18 months. or prior to operation after ECCS piping has been drained by verifying that the ECCS piping is full of water by venting the ECCS pump casings and discharge piping high points.
By a visual inspection which verifies that no loose debris (rags, c.
trash, clothing, etc.) is present in the containment which could be transported to the containment energency sump and cause restriction of the pump suction during LOCA conditions. This visual inspection shall be performed:
1.
For all accessible areas of the containment prior to establish-ing CONTAINMENT INTEGRITY, and 2.
Of the areas affected within containment at the completion of each containment entry when CONTAINMENT INTEGRITY is established, d.
At least once per 18 months by:
1.
Verifying that the interlocks:
a) Close DH-11 and DH-12 and deenergize the pressurizer heaters, if either DH-ll or DH-12 is open and a simulated reactor coolant system pressure which is greater than the trip setpoint (<438 psig) is applied. The interlock to close DH-il and/or DH-12 is not required if the valve is closed and 480 V AC power is disconnected from its motor operators.
b) Prevent the opening of DH-11 and DH-12 when a simulated or actual reactor coolant system pressure which is greater than the trip setpoint (<438 psig) is applied.
2.
a) A visual inspection of the ' containment stergency sump which verifies that the subsystem suction inlets are not restricted by debris and that the sump components (trash racks, screens, etc.) show no evidence of structural distress or corrosion.
b) Verifying that on a Borated Water Storage Tank (BWST) Low-Low Level interlock trip, with the motor operators for the BWST outlet isolation valves and the containment emergency sump recirculation valves energized, the BWST Outlet Valve HV-DH7A (HV-DH78) automatically close in sJS seconds after the operator manually pushes the control switch to open the Containment Emergency Sump Valve HV-DH9A (HV-DH98) which should be verified to open in <75 seconds.
- 2. he.\\e.Nt.b Z V e r i fying-a-total-4eak-rat @O-94444RG-Pe40ur-4er---the44
-sys-ten-at+
-4)
"^m:! cptritig pretture cr hydrettatic tett precture c' 1150 p-19-for those par-ts-of-the-+ystem-downstream-of4 pump suction isolation-valve -and r
~ b)
~H5 prig fer the piping-f-rom-the-contauvnent-emeegency Sump 4olat4en-va4ve-to-the-pump 4uction 4MI44to#-V44%
DAVIS-BESSE, UNIT I 3/4 5-4 Amendment No. 3,25,78,M,77 /1A5,182 i
Docket Number 50-346 Licensa Number NPF-3
)
S: rial Number 2252 Attschment ADDill0NAL CilANGES PREVIOUSLY Pm 10 CHERGE [Y CORE CZLING SYSTEMS PROPOSED BY LETTER Serial No.
17__ (o Date 2/tzjg j SURYEILL ANCE ?EC'.'!Rif1ENT (2ntiruedl 11 y
4.
Verifying that a minimum of 72 cubic feet of solid granular trisodium phosphate dodecahydrate (TSP) is contained within the a
. TSP storage baskets.
5.
Verify that a representative sample of TSP from a TSP storage basket has a density of > 53 lbs/cu ft.
6.
Verifying that when a' representative sample of 0.35 1 0.05 lbs of TSP from a TSP storage basket is submerged, without a5 tation, in 5015 gallons of 180110*F borated water i
from the BWST, the pH of the mixed solution is raised to,
> 6 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
At least once per 18 months, during shutdown', by e.
1.
Verifying that each automatic valve in the flow path actuates to its correct position on a safety injection
. test signal.
2.
Verifying that each HPI and LPI pump starts auto-matica11y upon receipt of a SFAS test sign,al.
By performing a vacuum leakage rate test of the watertight f.
enclosure for valves DH-11 and DH-12 that assures the motor operators on valves DH-11 and DH-12 will not be flooded for at least 7 days following a LOCA:
1.
At least once per 18 months.
Aftereachopeningofthe~watertightenclos0/e.
2.
3.
After any maintenance on or modification to the watertight enclosure which could affect its integrity.
By verifying the correct position of each mechanical position g.
stop for valves DH-14A and DH-14B.
1.
Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following completion of the opening of the valves to their mechanical position stop or following completion of maintenance on the valve when the LPI system is required to be OPERABLE 2.
At least onc'e per 18 months.
Ills PAGE PROVIDED
[
F01INFORBil0N ONlY 3,a,.e
..,nement Rc.
s <e i;ma1.e<1<.cx:s,
Docket Number 50-346 License Number NPF-3 Sarial Number 2252 iWIS PAGE PROVIDED Attachment FORINF0H" Allt'NDNF EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) h.
By performing a flow balance test, during shutdown, following completion of modifications to the HPI or LPI subsystems that alter the subsystem flow characteristics and verifying the following flow rates:
HPI System - Single Pump Injection Leg 1-1 1 375 gpm at 400 psig*
Injection Leg 1-2 1 375 gpm at 400 psig*
Injection Leg 2-1 1 375 gpm at 400 psig*
Injection Leg 2-2 1 375 gpm at 400 psig*
LPI System - Single Pump
]
injection Leg 1 1 2650 gpm at 100 psig**
l Injection Leg 2 1 2650 gpm at 100 psig**
1 Reactor coolant pressure at the HPI nozzle in the reactor coolant pump discharge.
Reactor coolant pressure at the core flood nozzle on the reactor vesser:
DAVIS-BESSE, UNIT 1 3/4 5-Sa Amend:nent No. 20
% r
Docket Number 50-346 License Number NPF-3 THiS PAGE P,il0sVsD*tD I
Serial Number 2252
- v"'
FORINFORMATi0N DN0'
~
00NTAltW.ENT SYSTEMS 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS ONTAINMENT SPRAY SYSTEM
^
LIMITING CONDITION FOR OPERATION Two indepencent containment spray systems shall be OPERABLE
.6.2.1 ith each spray system capable of taking suction from the BWST on a 3
entainment spray actuation signal arid manuallp transferring suction s
o the containment emergency sump during the recirculation phase of t
]peration.
APPLICABILITY.: MODES 1, 2, 3 and 4.
ACTION _:
4f th one containment spray system inoperable, restore the inoperable spray system to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at lea'st HOT STAND 8Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore the inoperable spray system to OPERABLE status within the next 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in COLD SHUTOO dithin the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVElLLANCE REQUIREMENTS Each containment spray system shall be demonstrated OPERABLE:
4.6.2.1 At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that a.
is not locked, sealed or otherwise secured in position, is in its correct position.
At least once per 18 months, during shutdown, by:
b.
Verifying that each automatic valve in the flow path 1.
actuates to its correct position on a containment spray test signal.
Verifying that each spray pump starts automatically on 2.
a SFAS test signal.
DAVIS-BESSE, UtilT 1 3/4 6-11 Amendment No. 36
Docket' Number 50-346 License Number NPF-3 S2 rial Number 2252
-Attschment Page 13 CO.:T A!!;'4ENT SYSTE_MS SUR_VE1LLANCE REQUIREMENTS (Continued) he. \\e.ke d.
At -l es:t ;r.:c per 18 enth: by verifying a total le:E rate-c.
g 1 20 g:llcr.: per Scur fcr th: yct:- 44:
hydr +M+t4e-test pressure
-1.
Mem:1 oper+ tim::ere er :Of th: :y:tc dcwr.streca, er cf ; 150 p:!g fer thc:: p:rt:
the pump cuctic: 9.c12tien valv:, and 1 'S prig for the piping ' rem the cent:4reent : :rgencytc the pump sectier i:c?:
2.
-: ump i:012 tion valv:
At least oncd per 5 years by performing an air or smoke flow test through each spray header and verifying each spray nozzle d.
is unobstructed.
I DAVIS-BESSE. UNIT 1 3/4 6-12
Docket Number 50-346 License Number NPF-3 Serial Number 2252
- t"'
gg PABE PROMDED-fBRINf3 EON ONE 3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)
BASES 3/4.5.
CORE FLOODING TANKS ine OPERABILITY of each core flooding tenk ensures that a sufficient volume of borated water will be immediately forced into the reactor vessel in the event the RCS pressure falls below the pressure of the tanks.
This initial surge of water into 'the vessel provides the initial cooling mechanism during large RCS pipe ruptures.
The limits on volume, boron concentration and pressure ensure that the assumptions used for core flooding tank injection in the safety analysis are met.
l The tank power operated isolation valves are considered to bc
" operating bypasses" in the context of IEEE Std. 279-1971, which requires 1
that bypasses of a protective function be removed automatically whenever l
pennissive conditions are not met. In addition, as these tank isolation I
valves fail to meet single failure criteria, removal of power to the valves is required.
The limits for operation with a core flooding tank inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a LOCA event occurring concurrent with failure of an additional tank which may result in unacceptable peak cladding tempera-tu res. If a closed isolation valve cannot be immediately opened, the full capability of one tank is not available and prompt action is required to place the reactor in a mode where this capability is not required.
3/4.5.2 and 3/4.5.3 ECCS SUBSYSTEMS The OPERABILITY of two independent ECCS subsystems with RCS average temperature > 280*F ensures that sufficient emergency core cooling capaulity wTil be available in the event of a LOCA assuming the loss of, one subsystem through any single failure consideration. Either subsystem opereeing in conjunction with the core flooding tanks is capable of supplying sufficient core cooling to maintain the peak cladding tempera-tures within acceptable limits for all postulated break sizes ranging from the double ended break of the largest RCS cold leg pipe downward.
In addition, each ECCS subsystem provides long term core cooling capability in the recirculation mode during the accident recovery period.
I DAVIS-BESSE. UNIT 1 8 3/4 5-1 Amendment No. 20 ADDITIONAL CHANCES PREYl0VStY PROPOSED BY LETIER Serial No._ 21 \\ 0 Date 2/71/j,y
Docket Number 50-346 License Number NPF-3 Serial Eumber 2252
^*** """*
ADDill0NAL CHANGES 7REV100 SLY Page 15 PROPOSED BY LETTER Date /zgqy 2
Serial No. 2-? t O -
EMERGENCY CORE COOLING SYSTEMS BASES With the RCS temperature.below -280*F, one OPERABLE ECCS subsystem is ac eptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.
The Surveillance Requirements provided to ensure OPERABILITY of each component ensures that, at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained. The d:::y ha t rc::=l '
Oy;;;: leah rat: ;urveillen;; c w 'rement: O nur; th:t th
!= hag; r:te:
e33u7.cd f;r th; ;y;t;;.d r'n; the retirculatien phn ef th0 l e pre:Sur n.,
inj;; tion will not b' cacc e d:d F Surveillance requirements for throttle valve position stops and flow balance testing provide assurance that proper ECCS flows will be maintained in the event of a LOCA. Maintenance of proper flow resistance and pressure drop in the piping system to each injection point is necessary to: (1) prevent total pump flow from exceeding runout conditions when the system is in its minimum resistance configuration, (2) provide the proper flow split between injection points in accordance with the assupptions used in the ECCS-LOCA analyses, and (3) provide an acceptable level df total ECCS flow to all injection points equal to or above that assumed in the ECCS-LOCA analyses.
Containment Emergency Sump Recirculation Valves DH-9A and DH-98 are de-energized during MODES 1, 2, 3 and 4 to preclude postulated inadvertent opening of the valves in the event of a Control Room fire, which could result in draining the i
Borated Water Storage Tank' to the Containment Emergency Sump and the loss of this water source for nonnal plant shutdown. Re-energi2ation of DH-9A and DH-9B is pennitted on an intermittent basis during HODES 1, 2, 3 and 4 under administrative controls. Station procedures identi.fy the precautions which must be taken when re-energizing these valves under such controls.
Borated Water Storage Tank (BWST) outlet isolation valves DH-7A and DH-78 are de-energized during HODES 1, 2, 3, and 4 to preclude postulated inadvertent closure of the valves in the event of a fire, which could result in a loss of the availability of the BWST. Re-energization of valves DH-7A and DH-78 is permitted on an intermittent basis during H00ES 1, 2, 3, and 4 under adminis-trative controls. Station procedures identify the precautions which must be taken when re-energizing these valves under such controls.
3/4.5.4 BORATED WATER STORAGE TANK The OPERABILITY of the borated water storage tank (BWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA. The limit _s on BWST minimum volume and boron concentration ensure that 1) sufficient water is available within contaia.
ment to permit recirculation cooling flow to the core, and 2) the reactor will remain subcritical in the cold condition following mixing of the BWST and the RCS water volumes with all control rods inserted except for the most reactive control assembly. These assumptions are consistent with the LOCA analys es.
The bottom 4 inches of the borated water storage tank are not available, and the instrumentation is calibrated to reflect the available volume. The limits on water volume, and boron concentration ensure a pH value of between 7.0 and 1
11.6 of the solution sprayed within the containment a,f ter a design basis accident. The pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion cracking on mechanical systems and components.
DAVIS-BESSE. UNIT 1 B 3/4 5-2 gdgtg 2QZ tion Ltr 5/17/9 r
i l
~
bhcketNumber50-346 License Number NPF-3
.r:s hO bN ;1 -
% f.
i I dd i NI$U UJ Serial Number 2252
-asG f
Attachment trqi ig[fgM10N ONU
~
lU i
i CONTAINMENT SYSTEMS BASES 3/4.6.1.4 INTERNAL PRESSURE The limitations on contairment internal pressure ensure that 1) the containment structure is prevented from exceeding its design negative pressure differential with respect to the annulus atmosphere of 0.5 psi and 2) the containment peak pressure does not exceed the design pressure of 40 psig during LOCA conditions.
The maximum peak pressure obtained from a LOCA event is 37 psig.
The limit of 1 psig for initial positive containment pressure will limit the total pressure to 38 psig which is less than the design pressure and is consistent with the safety analyses.
3/4.6.1.S AIR TEMPERATURE The limitations on containment average air temperature ensure that j
the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA.
3/4.6.1.6 CONTAINMENT VESSEL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the contain-ment steel vessel will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the vessel will withstand the maximum pressure of 38 psig in the event of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.1.7 CONTAINMENT VENTILATION SYSTEM The limitation on use of the Containment Purge and Exhaust System limits the time this system may be in operation with the reactor coolant system temperature above 200'F. This restriction minimizes the time -
that a direct open path would exist from the contain:nent atmosphere to the outside atmosphere ar.) consequently reduces the probability that an accident dose would exceed 10 CFR 100 guideline values in the event of a LOCA occurring coincident with purge system operation. The use of this system is therefore restricted to non-routine usage not to exceed 90 l
hours in any consecutive 365 day period which is equivalent to approximately 1% of the total possible yearly unit operating time.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS 3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the containment spray system ensures that contain-ment depressurization and cooling capability will be available in the event of a LOCA. Ths pressure reduction and resultant lower containment DAVIS-BESSE, UNIT 1 B 3/4 6-2 Amendment No.135
Docket Number 50-346 License Number NPF-3 Serial Number 2252 Attachment Page 17 l
CONTAINMENT SYSTEMS-
{
BASES leakage rate are consistent with the assumptions used in the safety analyses.
Thc ic k rat: Or;; iller.00 requirrents ?ssure that the leakab.......-... she-eye + = d"H9 the reirculation phne " not 5: ::::cd:d.
Borated Water Storage Tank (BWST) outlet. isolation valves DH-7A and DH-78 are ide-energized during MODES 1, 2, 3, and 4 to preclude postulated inadvertent
, closure of the valves in the event of a fire, which could result in a loss of
- the availability of the BWST. Re-energization of valves DH-7A and DH-78 is
' permitted on an intermittent basis during MODES 1, 2, 3 and 4 under admints-ltaken when re-energizing these valves under such controls.
trative controls. Station procedures identify the precautions which must be Containment Emergency Sump Recirculation Valves OH-9A and DH-9B are de-ener-gized during MODES 1, 2, 3, and 4 to preclude postulated inadvertent opening, of the valves in the event of a fire, which could result in draining the Borated Water Storage Tank to the Containment Emergency Sump and the loss of this water source for normal plant shutdown. Re-energization of valves DH-9A and DH-98 is permitted on an intermittent basis during MODES 1, 2, 3, and 4 under administrative controls. Station procedures identify the precautions which must be taken when re-energizing these valves under such controls.
3/4.6.2.2 CONTAINMENT COOLING SYSTEM The OPERABILITY of the containment cooling system ensures that 1) the containment' air temperature will be maintained within limits during normal operation, and 2) adequate heat removal capacity is available when operated in conjunction with the containment spray systems during post-LOCA conditions.
)
3/4.6.3 CONTAINMENT ISOLATION VALVES The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the Sontainment atmosphere or pressurization of the containment. Containment isolation within the required time limits specified ensures that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
Containment isolation valves and their required isolation times are addressed in the USAR. The opening of a closed inoperable containment isolation valve on an intermittent basis during plant operation is permitted under administrative i
control. Operating procedures identify those valves which may be opened under administrative control as well as the safety precautions which must be taken when opening valves under such controls.
DAVIS.BESSE, unlT 1 B 3/4 6-3 Amendment No. J35, f17,182
docket' Number 50-346 License Number NPF-3 Strial Number 2252
- T"E IlilS PAGE PROVIDED
=
r Fs'"
585- - "'
ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The f acility shall be placed in at least HOT STANDBY within one hour.
a.
b.
The Safety Limit violation shall be reported to the NRC Operations Center by telephone as soon as possible and in all cases within one In addition the Vice President Nuclear and the CHRB shall be hour.
notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A Safety Limit Violation Report shall be prepared. The report shall c.
be reviewed by the SRB. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
The Safety Limit Violation Report shall be submitted to the d.
Commission, the CNRB and the Vice President, Nuclear within 14 days of the violation.
6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory a.
Guide 1. 33, November,1972.
l b.
Refueling operations.
Surveillance and test activities of safety related equipment.
c.
d.
Industrial Security Plan implementation.
l Davis-Besse Emergency Plan implementation.
l e.
f.
Fire Protection Program implementation.
)
The radiological environmental monitoring program.
9 h.
i.' Offsite Dose Calculation Manual implementation.
Each procedure of 6.B.1 above, and changes thereto, shall be reviewed 6.8.2 and approved prior to implementation as set forth in 6.5.3 above.
DAvl5-BE55E, UNIT 1 6-13 Amendment No. 9.12.27.E6.98.109, L
139 l '
D6ckst' Number 50-346 Licznse Number NPF-3 "HIS MGE PRH. DED Strial Number 2252
=nr"'.
FORIN!0RK0N ONlY ADMINISTRATIVE CONTROLS 6.8.3 (deleted)
The following programs shall be established, implemented and
6.8.4 maintained
Primary Coolant Sources outside Containment a.
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 lov as practical The systems include makeup, letdown, seal injection, levels.
seal return, low pressure injection, containment spray, high pressure injection, vaste gas, primary sampling and reactor The program shall include the following:
coolant drain systems.
Preventive maintenance and/or periodic visual inspection (1) l requirements, and (ii) Integrated leak test requirements for each system at refueling cycle intervals or less.
I
(
b.
In-Plant Radiation Monitoring A program which vill ensure the capability to accurately deter-mine the airborne iodine concentration in vital areas under This program shall include the following:
accident conditions.
(1)
Training of personnel.
(ii)
Procedures for monitoring, and Provisions for saaintenance of sampling and analysis (iii) equipment.
9.12.IldS' Amendment No.
A 34
_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _