ML19305E764
| ML19305E764 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/29/1980 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19305E765 | List: |
| References | |
| TAC-52692, NUDOCS 8005200381 | |
| Download: ML19305E764 (18) | |
Text
-
80 052 o n.3gl CV"%o,h P
+
UNITED STATES 1
~
8 NUCLEAR REGULATOHY COMMISSION c,
g
- E WASHINGTON, D. C. 20556
$,l.h,$
WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. DPR-24 1.
The Nuclear Regulatory Comrission (the Commission) has found that:
A.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; B.
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; C.
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 D.
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 amend-ment, and paragraph 3.B of Facility Operating License No. DPR-24 is hereby amended to read as follows:
(b) TechnicalSpecifcations The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 44,are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
i t
. 3.
This ifcense amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ada'&v A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors 4
i
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 29,1980 i
I i
)
i
t i
ATTACHMENT TO LICENSE AMENDMENT i
AMENDMENT NO. 44 TO FACILITY OPERATING LICENSE NO. DPR-24 DOCKET NO. 50-266 j
Revise Appendix A as follows:
Remove Pages
. Insert Pages 15.2.3-2 15.2.3-2 15.3.1-1 15.3.1-1 15.3.1-2 15.3.1-2 15.3.1-3 15.3.1-3 15.3.1-19 l
15.4.3-1 15.4.3-1 2
I
--..--e.
,a.g,
-,-g-e-
r-,----
,.,,,ay--
,---e
,-e n
r
(3) Low pressurizar pressora - > 1790 psig for operation at 2000 psia primary system pressure (4) Overtemperature AT STo(K1 - K (T-T' ) (1 +t 3 Si + K3(P-P')-f(AI))
2 1+t2S where ATo = indicated AT at rated power
'F average temperature. 'F
.T
=
T' 574.2 'F
=
P pressurizer pressure, psig
=
P' 2235 psig
=
K11 1.30 for operation at 2000 psia prithary system pressure 0.0150 K2
=
K3 0.000791
=
tj 25 see
=
t2 3 see
=
and f(AI) is an even function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured instrument response during plant startup tests, where qt and qb are the percent power in the top and bottom halves of the core respectively, and qt + 9b is total core power in percent of rated power, such that:
(a) for qt ~ 9bwithin-17,+9 percent,f(AI)=0.
(b) for each percent that the magnitude of qt ~9b exceeds +9 percent the AT trip set point shall be automatically reduced by an equivalent of two percent of rated power.
15.2.3-2 Amendme,nt -No. 44, Unit 1
15.3 LIMITING CONDITIONS FOR OPERATION 15.3.1 REACTOR COOLANT SYSTEM Applicability Applies to the operating status of the Rea~ctor Co,. ant System.
_ Objective To specify those limiting conditions for operation, of the Reactor Coolant System which must be, met to ensure safe reactor operation.
Specification A.
OPERATIONAL COMPONENTS Specification:
1.
Coolant Pumps a.
At least one reactor coolant pump or the residual heat removal system shall be in operation when 6 reduction is made in the baron concentration of the reactor coolant.
i b.
When the reactor is critical and above 1% thermal power, except for natural circulation tests, at least one reactor coolant pump shall be in operation.
c.
(1) Reactor power shall not be maintained above 10%
of rated power unless both reactor coolant pumps are in operation.
(2) If either reactor coolant pump ceases operating, ininediate power reduction shall be initiated under administrative control as necessary to reduce power to less than 10% of rated power.
2.
One steam generator shall be operable whenever the average reactor coolant temperature is above 350'F.
15.3.1-1 Amendment No. 44, Unit 1
3.
Safety Valves a.
At least one pressurizer safety valve shall be operable when,ever the reactor head is on the vessel.
b.
Both pressurizer safety valves shall be operable whenever the reactor is critical.
Basis:
When the boron concentration of the reactor coolant system is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor. Mixing of the reactor coolant will be sufficient to maintain a uniform boron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place.
The residual heat removal pump will. circulate the primary system volume in approximately one half hour. The pressurizer is of little concern because of the low pressurizer volume and because pressurizer baron concentration normally will be higher than that of the rest of the reactor coolant.
l 15.3.1-2 Amendment No. 44, Unit 1
l Part 1 of tha specification requires that a sufficient number of reactor coolant pumps be operating to provide core cooling in the eveat that a loss of flow occurs. The flow provided in each case will k(ep DNBR well above 1.30 as discussed in FFDSAR Section 14.1.9. Therefore, cladding damage and release of fission products to the reactor coolant will not occur. Heat transfer analyses (1) show that reactor heat equivalent to 10% 6f rated power can be removed with natural circulation only; hence, the specified upper limit of 1%
rated power without operating pumps provides a substantial safety factor.
Each of the pressurizer safety valves is designed to relieve 288,000 lbs.
per hr. of saturated steam at set point. Below 350*F and 350 psig in the reactor coolant system, the residual heat removal system can remove decay heat and thereby control system temperature and pressure.
If no residual heat is removed by any of the means available the amount of steam which could be generated at safety valve relief pressure would be less than half the valves' capacity. One valve therefore provides adequate defense against over-pressuriza-tion. Part 1 c(2) permits an orderly reduction in power if a reactor coolant pump is lost during operation between 10% and 50% of rated power. Above 50%
power, an automatic reactor trip will occur if either pump is lost. The power-to-flow ratio will be maintained equal to or less thin 1.0 which ensures that the minimum DNB ratio increases at lower flow since the maximum enthalpy rise does not increase above its normal full-flow maximum value.(2)
Reference (1) FSAR Section 14.1.6 (2) FSAR Section 7.2.3 l
15.3.1-3 Amendment No. 44, Unit 1 I
~
6.
OPERATIONAL LIMITATIONS The following DNB related parameters shall be maintained within the limits i
shown during Rated Power coeration:
1.
TAVG shall be maintained at or below 578'F.
2.
Reactor coolant system pressure shall be maintained:
11955 psig' during operation at 2000 psia.
3.
Reactor Coolant System Total Flow Rate 1
1 78,000 gpm.
Basis:
Although the operational limitations above require reactor coolant system 1
total flow be maintained above a minimum rate. no direct means of measuring absolute flow during operation exist However, during initial startu '
reactor coolant flow was measurea and correlated to core AT. Therefore monitoring of AT may be used to verify the above minimum flow requirement is met.
If a change in steady state full power AT greater than 3 F is observed, the actual flow measurements will be taken.
15.3.1-19 Amendment No. 44, Unit 1
-- 1
15.4.3 PRIMARY SYSTEM TESTING FOLLOWING OPENING Applicability Applies to test requirements for primary systeni integrity.
Objective To specify tests for primary system integrity after the system is closed following normal opening, modification or repair.
Specification a)
When the primary system is closed after it has been opened, the system will be leak tested at -not less than 2085 psig for operation at 2000 psia primary system pressure.
b)
When primary system modifications or repairs have been made which involved new strength welds on components greater than 2 in. diameter, the new welds will receive both a surface and 100% volumetric non-destructive examination.
c)
When primary system modifications or repairs have been made which involve new strength welds on components 2 in. diameter or smaller, the new welds will receive a surface examination.
Basis For normal opening the integrity of the system, in terms of strength,is unchanged.
If the system does not leak at 2085 psig (operating pressure + 100 psi: + 100 psi
~
is normal system pressure fluctuation), it should be leak tight during normal operation at 2000 psia.
15.4.3-1 knendme'nt No. 44, Unit 1
pn utuq Th UNITED STATES
- w E $ e(- i NUCLEAR REGULATORY COMMISSION
- e )
E WASHWGTON. D. C. 20555 WISCONSIN ELECTRIC POWER COMPANY DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. DPR-27 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Wisconsin Electric Power Company (the licensee) dated November 2,1979, as supplemented November 27, December 14, 21 and 31,1979 and January 31, 1980, complies with the standards and requirements of the Ato.nic 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.
s j
w
i 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-27 is hereby amended to read as follows:
(B) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 49, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (lgd W W A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuancei April 29,1980 l
I 1
I
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 49 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NO. 50-301 i
Revise Appendix A as follows:
Remove Pages Insert Pages 15.2.3-2 15.2.3-2 15.3.1-1 15.3.1-1 15.3.1-2 15.3.1-2 15 J.1 -3 15.3.1-3 15.3.1-19 15.4.3-1 15.4.3-1 o
O l
- (3) Low pr0ssuriz'Ir pressora - 3,1865 p3fg f r cperati n et 2250
{
psia prisury systam pressure 3,1790 psig for operation at 2000 psia primary system pressure (4) Overtemperature AT gTo(K)-K(T-T')(1+t,S +K3(P-P')-f(AI))
2 1+t2S where ATo = indicated AT at rated power. F average temperature. 'F
.T
=
T' 574.2 0F
=
i P
pressurizer pressure, psig
=
P' 2235 psig
=
1 117 for operation at 2250 psia primary system pressure 1
- K) 1 1
30 for operation at 2000 psia primary system pressure P.0150 K2
=
0.00b791 K3
=
tj 25 see
=
2 3 see
=
t and f(AI) is an even function of the indicated difference between top and bottom detectors of the power-range nuclear ion chambers; with gains to be selected based on measured
)
i instrument response during plant startup tests, where qt and q3 are the percent power in the top and bottom halves of the core respectively, and qt + 9b is total core power in percent
^
of rated power, such that:
(a) for qt " 9bwithin-17.+9 percent,f(AI)=0.
(b) for each percent that the magnitude of qt -9b exceeds +9 percent the AT trip set point shall be automatically reduced by an equivalent of two percent of rated power.
- Appropriate safety analyses shall be performed prior to shifting operation from one primary system pressure to the other.
15.2.3-2 Amendme,nt No. 49, Unit 2 l
15.3 LIMITING CONDITIONS FOR OPERATION 15.3.1 REACTOR COOLANT SYSTEM Applicability Applies to the operating status of the Rea~ctor Coolant Systs.
g ective To specify those limiting conditions for operation of the Reactor Coolant System which must be, met to ensure safe reactor operation.
Specification A.
OPERATIONAL COMPONEfRS Specification:
1.
Coolant Pumps a.
At least one reactor coolant pump or the residual heat removal system shall be in operation when a reduction is made in the baron concentration of the reactor coolant, b.
When the reactor is critical and above 1% thermal power, except for natural circulation tests, at least one reactor coolant pump shall be in operation.
c.
(1) Reactor power shall not be maintained above 10%
of rated power unless both reactor coolant pumps are in operation.
(2) If either reactor coolant pump ceases operating, imediate power reduction shall be initiated under administrativi control as necessary to reduce power to less than 10% of rated power.
2.
One steam generator shall be operable whenever the average reactor coolant temperature is above 350 F.
15.3.1-1 Amendment No. 49, Unit 2
3.
Safety Valves At least one pressurizer safety valve shall be operable a.
whenever the reactor head is on the vessel.
b.
Both pressurizer safety valves shall bs operable whenever the reactor is critical.
Basis:
When the boron concentration of the reactor coolant system is to be reduced the process must be uniform to prevent sudden reactivity changes in the reactor. Mixing of the reactor coolant will be sufficient to maintain a uniform baron concentration if at least one reactor coolant pump or one residual heat removal pump is running while the change is taking place.
The residual heat removal pump will circulate the primant system volume in approximately one half hour. The pressurizer is of little concern because of the low pressurizer volume and because pressurizer boron concentration normally will be higher than that of the rest of the reactor coolant.
15.3.1-2 Amendment No. 49, Unit 2
Part 1 of the specification requires that a sufficient number of reector coolant pumps be operating to provide core cooling in the event that a loss of flow occurs. The flow provided in each case will kfep DN8R well above 1.30 as discussed in FFDSAR Section 14.1.9. Therefore, cladding damage and release l
of fission products to the reactor coolant will not occur. Heat transfer analyses (1) show that reactor heat equivalent to 10% 6f rated power can be removed with natural circulation only; hence, the specified upper limit of 1%
rated power without operating pumps provides a substantial safety factor.
Each of the pressurizer safety valves is designed to relieve 288,000 lbs.
per hr. of saturated steam at set point. Below 350*F and 350 psig in the reactor coolant system, the residual heat removal system can remove decay heat and thereby control system temperature and pressure.
If no residual heat is l
removed by any of the means available the amount of steam which could be generated at safety valve relief pressure would be less than half the valves' capacity. One valve therefore provides adequate defense against over-pressuriza-tion. Part 1 c(2) permits an orderly reduction in power if a reactor coolant pump is lost during operation between 10% and 50% of rated power. Above 50%
power, an automatic reactor trip will occur if either pump is lost. The power-to-flow ratio will be maintained equal to or less thin 1.0 which ensures that the minimum DNB ratio increases at lower flow since the maximum enthalpy rise does not increase above its normal full-flow maximum value.(2)
~
Reference (1) FSAR Section 14.1.6 (2) FSAR Section 7.2.3 15.3.1-3 Amendment No. 49, Unit 2
G.
OPERATIONAL LIMITATIONS The following DNS related parameters shall be maintaine6 within the limits shown during Rated Power operation:
1.
TAVG shall be maintained at or below 578'F.
- 2.
Reactor coolant system pressure shall be maintained:
2; 2205 psig during operation at 2250 psia or, 2; 1955 psig' during operation at 2000 psia.
3.
Reactor Coolant System Total Flow Rate > 178,000 gpm.
Basis:
Although the operational limitations above require reactor coolant system total flow be maintained above a minimum rate, no direct means of measuring absolute flow during operation exist However, during initial startup' i
reactor coolant flow was measured and correlated to core AT. Therefore monitoring of AT may be used to verify the above mininum flow requirement is met.
If a change in steady state full power AT greater than 3 F is observed, the actual flow measurements will be taken.
l
- See footnote, page 15.2.3-2 15.3.1-19 Amendment No. 49, Unit 2 1
15.4.3 PRIMARY SYSTEM TESTING FOLLOWING OPENING Applicability Applies to test requirements for primary systeri integrity.
Objective To specify tests for primary system integrity after the system is closed following normal opening, modification or repair.
Specification a)
When the primary system is closed after it has been opened, the system will be leak tested at:
1)
Not less than 2335 psig for operation at 2250 pria primary system pressure, or 2)
Not less than 2085 psig for operation at 2000 psia primary system pressure.
b)
When primary system modifications or repairs have been made which involved new strength welds on components greater than 2 in. diameter, the new welds will receive both a surface and 100% volumetric non-destructive examination.
c)
When primary system modifications or repairs have been made which involve new strength welds on components 2 in. diameter or smaller, the new welds will receive a surface examination.
Basis For normal opening the integrity of the system, in terms of strervth,is unchanged.
If the system does not leak at 2335 psig (operating pressure + 100 psi: + 100 psi
~
j is normal system pressure fluctuati0n), it should be leak tight during normal operation at 2250 psia.
If the system does not leak at 2085 it should be bak tight during normal operation at 2LJO psia.
15.4.3-1 Amendment No. 49, Unit 2
_--- -- _ _