ML20238E064
| ML20238E064 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 09/02/1987 |
| From: | Virgilio M Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20238E067 | List: |
| References | |
| TAC-64851, NUDOCS 8709140107 | |
| Download: ML20238E064 (10) | |
Text
- _ _ _ _ - _.
~
C
\\j UNITED STATES
[s+ -[.g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555
%,#..../
TOLEDO EDISON COMPANY AND THE CLEVELAhD ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.103 License No. NPF-3 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Toledo Edison Company and The Cleveland Electric Illuminating Company (the licensees) l l
dated February 18, 1987, complies with the standards and' requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.103, are hereby incorporated in the license.
The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.
8709140107 870902 PDR ADOCK 05000346 PDR
__P______________
- i.
- g,
.b:
2-i 3.
-This license amendment is effective as of.its date of issuance and shall
'be' implemented not'later than October 2, 1987.
FOR'THE NUCLEte REGULATORY COMMISSION j
- r. h, ' _
6.
-Marti J.=Virgi io, Director l l
Project Directorate III-1 J
~
Division of Reactor Projects - III, IV, V
& Special Projects
Attachment:
' Changes to the'; Technical
')
Specifications Date of' Issuance:.. Se p tembe r 2,.1987 5
,\\
si.;
ATTACHMENT T0 LICENSE AMEN 0 MENT NO. 103-FACILITY OPERATING LICENSE NO. NPF-3 p0CKETNO.'50-346 l
o Replace'the following pages of:the. Appendix "A" Technical = Specifications with the attached-pages.l The: revised pages'are identified by Amendment number and.
L contain' vertical ~ lines' indicating the area of_ change.
The corresponding overleaf page(s) are-also provided to maintain document' completeness.
Remove-Insert a
VII-VII 3/4 7-12a 3/4 7-12b 3/4 7-12c B 3/4 7-3 B 3/4 7 -
y i
la
. _ _ _ _ _ - _. - _ = _ - _ _._
a.
L' I
INDEX
< LIMITING CONDITIONSFOR OPERATION AND: SURVEILLANCE REQUIREMENTS
-SECTION.
'PAGE
- 3/4.7 ' PLANT SYSTEMS-3/4.7.1' TURBINE CYCLE j
. Safety Valves:..
3/4 7-1 Auxiliary Feedwater System
~3/4 7-4'.
I Condensate' Storage Tank...
'3/4 7-6' 3/4 7-7 Accivity Main Steam.Line Isolation Valves 3/4 7-9 Secondary' Water Chemistry:..............
3/4 7-10
~
Motor Driven: Feedwater Pump System.
3/4 7-12a l
j 3/4.7.2-STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.
3/4 7-13 L
3/4.7.3 COMPONENT COOLING WATER SYSTEM 3/4 7-14.
.3/4 7-15 3/4.7.4' SERVICE WATER SYSTEM 3/4;7.5 ULTIMATE HEAT SINK 3/4 7-16L 3/4.7.6-CONTROL ROOM EMERGENCY VENTILATION SYSTEM.
3/4 7-17 3/4.7.7 ' HYDRAULIC SNUBBERS 3/4 7-20 3/4.7.8 SEALED SOURCE CONTAMINATION.
3/4 7-36 3/4.7.9 FIRE SUPPRESSION SYSTEMS
' Fire Suppression Water System.
3/4 7-38 Spray and/or Sprinkler System..
3/4 7-42 Fire Hose Stations 3/4 7-44 3/4.7.10 ' PENETRATION FIRE BARRIERS....
3/4 7-47 3/4.8 ELECTRICAL POWER SYSTEFS 3/4.8.1 A.C. SOURCES 1
Operating..
3/4 8-1 Shutdown 3/4 8-5 3 /4. 8. 2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. Distribution - Operating.
3/4 8-6 A.C. Distribution - Shutdown 3/4 8-7
~
D.C. Distr 1bution - Operating..
3/4 8-8 D.C. Distribution - Shutdown 3/4 8-10
' DAVIS-BESSE, UNIT 1 VII Amendment No. JHC 103
~~-
3~
p c7 1
4.
p.
a INDEX LIMITING C0b71TIONS FOR OPERATION AND SU*NEILL ANCE REQUIREMENTS SECTION A
. PAG _E 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................................
3/4 9-1 3/4.9.2 INSTRUMENTATION....................,.................
3/4 9-2 3/4.9.3 DECAY TIME..........................................
3/4 9-3 3/4.9.4 CONTAINMENT PENETRATIONS............,..................
3/4 9-4 7
7 3/4.9.5 COMMUNICATIONS............../......g................
3/4 9-5
- 4 3/4.9.6L FUEL HANDLING BRIDGE OPERABILITY. '
3/4 9-6 v
~
3/4.9. 7.
CRANE TRAVEL - FUEL HANDLING BUILDING................ 3/4 9-7 3/4.9.8 DECAY HEAT REMOVAL AND COOLANT CI'RCULATION l
i l
Al l Wa t e r Le ve 1 s..................................... 3/4 9-8 L ow W a t e r L e ve l...................................... 3/4 9-Ba 3/4.9.9 CONTAINMENT PURGE AND EXHAUST ISOLATION SYSTEM......
3/4.9-9 3/4.9.10 WATER LEVEL - REACTOR VESSEL........................
3/4 9-10 3/4.9.11 STORAGE POOL WATER LEVEL............................
J3/4 9-1) i 3/4.9.12 STORAGE POOL VENTILATION............................
3/,4 9-12 l
4 J'4.10 SPECIAL TEST EXCEPTIONS i
l 3/9.10.1 GROUP HEIGHT, INSERTION AND POWE R DI STRIBUTION LIMITS................... ~..... 3/4 10-1 3/4.10.2 PHYSICS TESTS.......................................
3/4 10-2 3/4.10.3 REAv.
1 Afri L 00 PS......................".........
3/4 10-3 3/4.10.4 S H UT OOWN MA R G I N..................................... 3/4 10-4 i
DAVIS-BESSE, UNIT 1 VIII Amendment No, gg,103
{*
.6 t
' x n
L PLANT SYSTEMS J
I MOTOR DRIVEN TEEDWATER PUMP SYSTEM j
s 1
I LIMITING CONDITION F00 OPERATION 3.7.1.7 TheMotorDr!. hen'FeedvaterPumpandassociatedflowpathtothe Auxiliary Teedvater System shall be' OPERABLE.
APPLICABILITY: MODES '1, 2, and 3.
flIJK:
With the Motor Driven Feedvater Pump or its associated flow path to the Aux 123.ary Feedvater System inoperable, restore 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 RCT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
r St'PVEILLANCE t.EOUIREMENTS 4.7.1.7 The required Motor Driven Feedvater Pump and flow path to the Auxiliary Teedvater System shall be demonstrated OPERABLE:
a.
At least once per 31 days by:*
1.
When the quarterly pump test is not performed, a Pump Jeg Test will be performed to verify the Motor Driven Teedvater Pump OPERABLE by starting the Motor Driven Feedvater Pump (if the pump is not already running) from
}
the control room, and by indication of flow.
2.
When in MODE 1 with RATED TRERMAL POWER greater than 40%,
verify that each manual valve in the Motor Driven Teedvater Pump suction and discharge lines that affect the system's f
capability to deliver water to the steam generators is locked in its proper positten for initial system operation.
3.
When in MODE 1 with RATED THERMAL POWER greater than 40%,
verify that each power operated valve in the flow path is in its correct position.
y 4
When in MODE I at RATED THERMAL POWER equal to or less than 40% or when in MODES 2 or 3 verify that each valve (manual 4
or power operated) in the Motor Driven Teedvater Pump flow path is able to be positioned locally for delivering flow to the Auxiliary Feedvater System.
- When conducting tests of the Motor Driven Teedvater Pump System in MODE 1 greater than 401 RATED THERMAL POWER which require local manual realign-ment of valves that make the system inoperable, a dedicated individual shall be stationed at the valves (in communication with the control room) oble to restore the valves to normal system OPERABLE status.
DA'JIS-BESSE, UNIT 1 3/4 7-12a Amendment No.103
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
(Ability is demonstrated by verifying the presence of handwheels for ell manual valves and the presence of either handwheels or available power supply for motor operated valves.)
b.
At least once per 92 days and prior to entry into MODE 3 from MODE 4 (if not performed in the past 92 days) by:
- and **
1.
Verifying proper operation of each power operated and automatic valve in the Motor Driven Feedwater Pump flow path to the Auxiliary Teedwater System.
2.
Verifying proper operation of the Motor Driven Teedwater Pump.
c.
At least once per 18 months by:
1 1.
Verifying that there is a flow path between the Motor
(
Driven Feedwater Pump System and the Auxiliary Teedwater System by pumping water from the Condensate Storage Tanks to the steam generators. The flow path to the steam generators shall be verified prior to entering MODE 3 from MODE 4 by either steam geners'ter level change or Auxiliary Feedvater flow indication. Verification of Motor Driven Teedwater Pump System flew capacity is not required.
2.
Verifying proper operation of the Motor Driven Teedwater Pump lube oil interlocks.
3.
Verifying proper operation of manual valves by shif ting the Motor Driven Feedwater Pump between the Main Teedwater System and the Auxiliary Teedwater System.
- When conducting tests of the Motor Driven Feedvater Pump System in NODE 1 greater than 401 RATED THERMAL POWER which require local manual realign-ment of valves that make the system inoperable, a dedicated individual shall be stationed at the valves (in communication with the control room) able to restore the valves to normal system OPERABLE status.
- If the Motor Driven Teedvater Pump cannot be tested within the time period specified, due to being aligned to the Main Teedwater System, the Surveillance Requirement shall be met within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after the Motor Driven Teedwater Pump has been aligned to the Auxiliary Feedvater System for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
1 DAVIS-BESSE UNIT 1 3/4 7-12b Amendment No.103 I
1 1
(;
s J'i
.s lt?
r pDNI SYSTEMS a
SURVEII.1.ANCE REQUIREMENTS (Coneinued) y' 1
d.
Af t2r'any modifienrien~ or iepair to the Motor' DrNan hedvater Pump System that ould aff ect the systea's capi.bility to deliver oter from the C6ndensate Storage "aaks to the Aailiary Feedvater 4
.Systes, the affected, f1rv path shall be demonstrated available ce follows ***
1.
if the modification or sepair is in the Auxiliary Feedvater flow path downstream of the Motor Driven Feedvater Pump test flov line tie-in, the Motor Driven Feedvater Pump shall pump water from the Condensate Storage Tanks to the
..uxiliary Feedvater System and the flow path availability eW5 6.
vf.11 be verified by either steam generator level change,or Aur.iiiary Feedvater flow indication.
I 2.
If the a, modification ers repair is upstream of the Motor Driven Feedvater. Pump test flov line tie-in, the Motor Driven Feedvgter Peep chall pump water,frua the fondtnsate
.s StorapoTanks to the t. net flov line atT the flow path availability:y will be verified by Motor Driven Fee.dymter Pump flow indication.
e.
Fe11oving each extended COLD SHUTDOWN (steater than 30 days in MODE 3), by:
1 1.
Verifying that' there is a flow path between the Motor Driven Feedvater Syrten and tby Auxiliary Feedvater System by pumping water fron the Conder. tate Storage Tanks to thw' 1
steam generators. The flow path to the steam generators shall be verified prior to entering MODE 3 from MODE 4 by either steam gen 6rator leve.1 change or Auxiliary Feedvater flow indication. Verifiestion of Motor Driven Feedvater Pump flow capacity is not required.
n,
/
1 I
- This surveillance testing shall be performed prior to enterict, MODE 3 from MODE 4 if the modification is made in MODES 4, 5. or 6.
Verifica-tion of the Motor Driven Feadutter Pump flow capacity is not required.
DAVIS-3 ESSE. UNU 1 3/4 7~ 12c Amendsent No.103 U
(Next page is 3/4 7-13)
o.
PLANT SYSTEMS BASES positive reactivity effects of the Reactor Coolant System cooldown associated with the blevdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within contain-ment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in the safety analyses.
3/4.7.1.6 SECORDARY WATER CHEMISTRY A test program will be conducted during approximately the first 6 months following initial criticality to establish the appropriate limits on the secondary water chemistry parameters and to determine the appropriate frequencies for monitoring these parameters. The results of this test program will be submitted to the Commission for review.
The Commission will then issue a revision to this specification specifying the listis on the parameters and the frequencies for monitoring these parameters.
The test program will include an analysis of the chemical constituents of the condanser cooling water at the point of intake. The analysis shall identify the various traces of ions which upon concentration in the condensate may have the potential for inducement for stress corrosion in the steam generator tubing. The test program shall also evaluate the efficiency of the water treatment systems in the facility for removal of such ions and the potential for addition of other ions resulting from the treatment method. The test program shall analyze concentration phenomena and the concentration rates in the steam generator and the secondary water system and shall consider concentration in the recircu-latir.g cooling water system.
3/4.7.1.7 MOTOR DRIVEN FEEDWATER PUMT SYSTEM i
The OPERABILITY of the Motor Driven Feedvater Pump System ensures that the Reactor Coolant System can be cooled down from normal operating conditions in the event of the total loss of Main Feedvater and Auxiliary Teedvater Pumps.
j i
The Motor Driven Feedvater Pump flow capability ensures that adequate j
feedvater flow is available to remove Decay Heat and reduce the Reactor Coolant System te=perature to where the Decay Heat System may be placed j
tinto operation.
When at 40% RATED THERMAL POWER or less and in MODES 1, 2. or 3. the Motor Driven Feedvater Pump System may be aligned to provide a flow path from the Deaerator Storage Tank through the Motor Driven Feedveter Pump i
i to the Main Feedvater System. During this Motor Driven Feedvater Pump mode of operation, a flow path from the Condensate Storage Tanks through the Motor Driven Feedvater Pump to the Auxiliary Feedvater System shall be maintained with the ability for manual positioning of valves such that DAVIS-BESSE. UNIT I B 3/4 7-3 Amendment No.103 1
e - :
i PLANT SYSTEMS
^
_ BASES the flow path esn be established. The ability for local, manual operation is demonstrated by verifying the presence of the handwheels for all manual valves and the presence of either handwheels or available power supply for motor operated valves.
3/4.7.2' STEAM GENERATOR PRESSURE / TEMPERATURE LIMITAT10h The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximun allowable fracture toughness stress limits. The limitations of 110'T and 237 psig are based on a steam generator RT j
of 40*F and are sufficient to prevent brittle fracture.
{
3/4.7.3 COMPONENT COOLING WATER SYSTEM.
The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure.
J is consistent with the assumptions used in the safety analyses.
3/4.7.4 SERVICE WATER SYSTEM The OPERABILIIT of the service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling f
capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
3/4.7.5 ULTIMATE HEAT SINK I
The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling capacity is available to either 1) provide normal cooldown of the facility, or 2) to mitigate the effects of accident conditions within acceptable limits.
1 The limitations on minimum water level and maximum temperature are
{
based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is 1
consistent with the recommendations of Regulatory Guide 1.27. " Ultimate Heat Sink for Nuclear Plants" March 1974.
3/4.7.6 CONTROL ROOM EKERGENCY VENTILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remsin habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisiens is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix "A",
10 CTR 50.
DAVIS-BESSE UNIT 1 53/47-4 Amendment No.103
PLANT SYSTEMS BASES the flow path can be established. The ability for local, manual operation is demonstrated by verifying the presence of the handvheels for l
all manual valves and the presence of either handvheels or available l
power supply for motor operated valves.
3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION l
The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum allevable fracture toughness stress limits. The limitations of Il0*F and 237 psig are based on a steam generator RT of 40*F and are sufficient to prevent brittle fracture.
NDT 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the component cooling water system ensures that sufficient cooling capacity is available for continued operation of safety related equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety :nalyses.
~
l 3/l. 7.4 SERVICE WATER SYSTEM The OP:tABILITY of the service water system ensures that sufficient cooling capacity is available for continued operation of safety related equipeent during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.
3/4.7.5 ULTIMATE HEAT SIh7 The limitations on the ultimate heat sink level and temperature ensure that sufficient cooling can tity is available to either 1) provide normal cooldown of the facilirf, or 2) to mitigate the effects of accident conditions within acceptable limits.
The limitations on minimum vater level and maximum temperature are based on providing a 30 day cooling water supply to safety related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, " Ultimate Heat Sink for Nuclear Plants" March 1974.
3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM The OPERABILITY of the control room emergency ventilation system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room vill remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is coesistent with the requirements of General Design Criterion 19 of Appendix "A",
10 CyR 50.
DAVIS-BESSE, UNIT 1 B 3/4 7-4 Amendwet No.103