ML20072R780
| ML20072R780 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/14/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072R783 | List: |
| References | |
| NUDOCS 8304060339 | |
| Download: ML20072R780 (12) | |
Text
~
g UNITED STATES 8
e NUCLEAR REGULATORY COMMISSION h
f WASHINGTON, D. C. 2006b e
g VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE ivnendment No 86 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Coninission) has found that:
A.
The application;for amendment by Virginia Electric and Power Company (the licensee) dated November 22, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter'I; B.
The facility will operate in confonnity with the. application, the provisions of the Act,~ and the rules and regulations of the Comnission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the' public, and (11) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendnent will not be inimical to the common defense and security o'r 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 requirenents have been satisfied.
e 6
8304060339 830314 PDR ADOCK 05000280 P
-,g,,.
(
[2-
~
2.
Accordingly, the license is amende( by changes to the Technical Specifications as indicated in the 'sc.tachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-32 is herehy amended to read as follows:
B.
Technical Specifications The Technical. Specifications contained in Appendix A, as revised through Amendment No. 86,"are herehy incorporated in the license. The licensee shall operate the facility. in accordance with the Technical Specifications.
3.
This itcense amendment is effective as of the date of its issuance.
FOR THE NUCLEAR G ATORY COMMISSION 1
)
gafC1 ve Operating Reactors Bran f #1 Division of Licensing
Attachment:
Changes to the Technical Specifications
~
Date of Issuance:
March 14,1983 N
g e
e ww - e
- g 7
/
\\
UNITED STATES NUCLEAR REGULATORY COMMISSION o
g a
wAsHWGTtm, D. C. 20885
(...../
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, ~ UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. DPR-37 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The appitcation;for amendment by Virginia Electric and Power Company (the licensee) dated Novenber 22, 1982, 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 ap' plication, the provisions of the Act, and the rules and. regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Commission's regulations; D.
The.fssuance of this amendnent 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.
O 9
e.
.wre
. +.
=f
=
4
s.
- 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license snendment, and paragraph 3.B of Facility Operating License No. DPR-37 is herehy amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 87..are herehy 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 NUCL /R REGULATORY COMMISSION' evenA(.Varga,Ch'e
.t" Operating Reacto s anch #1 Division of Licen in
Attachment:
Changes to the Technical Specifications Date of Issuance: Ma'rch 14,1983 i
f 1
.a y
. ~.
~,, ~
'n
~
l ATTACHMENTTOLICENSEANENDMENTS AMENDMENT NO. 86 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 87 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 2.1 -1 2.1 -1 2.1 -3 2.1-3 Figure 2.1-1 Figure 2.1-1 2.3-2 2.3-2 2.3-3 2.3-3 2.3-5
.2.3-5 6.5-3 6.5-3 t
n.
TS 2.1-1
~
2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS-s
~
2.1 SAFETY LIMIT, REACTOR CORE Applicability Applies to the limiting combinations of thermal power, Reactor Coolant System pressure, coolant temperature and toolant flow when a reactor is critical.
Objective To maintain the integrity of the fuel cladding.
. Specification A.
The combination of reactor thermal power level, coolant pressure, and coolant temperature shall not:
1.
Exceed the limits shown in TS Figure 2.1-1 when full flow from three. reactor coolant pumps exist.
2.
Excee'd the limits shown in TS Figure 2.1-2 when full f1'ow from two reactor coolant pumps exist and the reactor coolant loop stop valves in the non-operating loop are open.
3.
Exceed the limits shown in TS' Figure 2.1-3 when full flow from two reactor coolant pumps exist and the reactor coolant loop stop valves in the non-operating loop are closed.
Anendment Nos. 86 & 87
- W
-n r
t e
s TS 2.1-3 y
a
~~
uniform and non-uniform heat f" lux distributions. The local DNB heat flux ratio, defined as the ratio of the heat flux that would cause DNB at a particular core location to the actual heat flux, is indicative of the margin to DNB. The minimum value of the DNB ratio (DNBR) during steady state operation, normal operational transients and anticipated transients, is limited to 1.30.
A DNBR of 1.30 correspynds to a 95%.
probability at a 95% confidence level that DNB will not occur and is chosen as an appropriate margin to DNB for all operating conditions.
}
The curves of TS Figure 2.1-1 which show the allowable power level decreasing with increasing temperature at selected pressures for constant a
flow (three loop operation) represent limits equal to, or more conservative than, the loci of points of thermal power, coolant system average temperature, and coolant system pressure,for which the DNB ratio is equal to 1.30 or the average enthalpy at the exit of the core is equal to the saturation value.
The area where clad integrity 'is assured is below these lines.
The temperature limits 'are considerably more conservative than would be required if they were based up'on a minimum DNB
~
ratio of 1.30 alone but are such that the plani conditions required to violate the limits are precluded by the self-actu,ated safety valve's on the steam generators.
The three loo'p operation safety limit curve has been revised to allow for heat flux peaking effects due to fuel densification and to apply to 100% of design flow.
The effects of rod.
1 i
bowing are also considered in the DNBR analyses.
The curves of TS Figures 2.1-2 and 2.1-3 which show the allowable power i
level decreasing with increasing temperature at selected pressures for constant flow (two loop operation), represent limits equal to, or more conservative.
Amendment Nos, 86 & 87 g
e WW y
e a
TS Figuro 2.1-1 4
i 670 660 2400
- SI A G50 2200 n.
n o 8 630 2000 u
ASI A 620 C
I855 pg#
w 4
610 m
N 600
'{-
W zo 7
590 aW 3
580 W.
W E
570
=
W>
i 560.
l 550 1
I f
f I
I f
"I f
f f
f 0
10 20 30 40 50 60 70 80 90 100 110 120-POWER (PCRCCNT OF RATED)
FIGURI 2.1-1 REACTOR CORI THIRMAL & hTDRAULIC SAFITY LIMITS-THREE LOOE OPERATION, 100T FLOW Amendment Nos;.86 & 87 w.
-e p
.. D
,7 TS,2.3-2 i
(b) High pressurizer pressure - f 2385 psig.
(c) Low pressurizer pressure,- h 1860 psig.
(d) Overtempe'ature AT r
g - K (f +* < S A
o [K S )-(T - T') + K (P - P9 - $ 1)]
2 3
where AT, = Indicated AT at rated thermal power, *F T = Average coolant tempera.ture. *F' T'= 574.4*F P = Pressurizer pressure, psig P= 2235 psig K = 1.12 g
K = 0.01012 2
K = 0.000554 for 3-loop operation 3
K = 0.951
~
g K = 0.01012 for 2-loop operation vith loop stop 2
K = 0.000554 valves open in inoperable loop 3
K = 1.026 g
K = 0.01012 for 2-loop operation with loop stop.
2 K = 0.000554 valves closed in inoperable loop 3
t " 9, where q and qb are the percent power in the top and AI = q b
g bottom halves of the core respectively, and q +
g qb ih t tal core power in percent of rated power
'f(AI) = function ofAI, percent of rated core power as shown in Figure 2.3-1 4 = 25 seconds 3
4 = 3 seconds 2
(e) Overpower AT
-K(
3
)T-K6(
'} ~ ' ('I)3 ATg&T, [K4 5
~
1+4S3 Amendment Nos. 86 & 87 em e
- Y
- . o.
. r-TS 2.3-3 where
, AT, = Indicated AT at fated thermal! power, 'F T = Average coolant temperature. 'F T' = Average coolant temperature measured at nominal conditions and rated power, *F K4 = A constant = 1.09 K5 ".0 for' decreasing average temperature A constant, for' increasing average temperature 0.02/*F
~
K6 = 0 for TfT'
= 0.00108 for T>T' f(AI) as defined in (d) above.
<3 = 10 seconds (f) Low reactor coolant loop flow - 290% of normal indicated loop flow as measured'at elbow taps in each loop (g) Low reactor coolant pump motor frequency - 157.5 Hz (h) Reactor coolant pump under voltage - 270% of normal voltage 3.
Other reactor trip settings (a) High pressurizer water level - $92% of span (b) Low-low steam generator water level -25% of narrow range instrument span (c) Low steam generator water level - 315% of narrow range instrument span in coincidence with steam /feedwater 0
mismatch flow - fl.0x10 lbs/hr
~
(d) Turbine trip (e) Safety injection - Trip settings for Safety Injection are detailed in TS Section 3.7.
Amendment Nos. 86 & 87 e
s o
- W
-- 9
- w
v-TS 2.3-5 and source range high flux, high setpoint trips provida additional
~
protection against uncontrolled startup excursions.. As power level increases, during startup, these trips are blocked to prevent vanecessary plant trips.
l The high and low pressurizer pressure reactor trips limit the pressure range in which reactor operation is permitted.
The high pressurizer pressure reactor trip is also a backup to the pressurizer cede safety valves for overpressure protection, and is therefore se,t lower than the set pressure for these valves (2485 psig).
The low pressurizer pressure reactor trip also trips the reactor in the unlikely event of a loss-of-coolant accident.( }
The overtemperature AT' reactor _ trip provides core protection against DNB for all combinations of pressure, power, coolant temperature, and axial power distribution. provided ' only that the transient is slow with respect to piping transit delays from the core to the temperature detectors (about 3 seconds), and pressure is within the range between
.high and low pressure reactor trips. With normal axial power distri-(}
bution, the reactor trip limit, with allowance for errors.
is always below the core safety limit as shown on. TS Figure 2.1-1.~
If axial peaks are greater the design, as indicated by the difference between top and bottom power range nuclear detectors, the reactor limit is automatically reduced. (4)(5)
G The overpower and overtemperature protection system setpoints have been revised to include effects of fuel densification on core safety limits and to apply to 100% of design flow.,The revised setpoints in the Technical Specifications will ensure that the ' combination of power, temperature', and pressure will nat exceed the revised Amendment Nos. 86 & 87 L --
-2
=
TS 6.5-3 i
9.
Records of the service lives of all hydraulic and mechanical snubbers listed on Tables 4.17-1, 4.17-2, including the date at which the service life commences and associated installation and maintenance redords.
10.
Records of the annual audit o'f the Station Emergency Plan and implementing procedures.
11.
Records of the annual audit of the Station Security Pl~an and implementing procedures.
.}
E Amendment Nos. 86 & 87
....