ML19209A164
| ML19209A164 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/06/1979 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19209A165 | List: |
| References | |
| NUDOCS 7910030042 | |
| Download: ML19209A164 (9) | |
Text
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UNITED STATES es v 't NUCLEAR REGULATORY COMMISSION j.I(J.f,i ;
WASHINGTON, D. C,20555
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT N0. 1 AfENDMENT TO FACILITY OPERATING LICENSE Amendnent No. 52 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated August 8,1979, 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 3pplication, 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 anencment can be conducted without endangering t'e 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 a~
dance with 10 CFR Part 51 of the Commi::icn's regulations end all applicable requirements have been satisfied.
1084 253 7 91003 00 %-
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, 2.
Accordingly, the license is amended by chang'es to the Technical Specifications as indicated in the attachment to the license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications centained in Appendices A and B, as revised through Amendment No. 52, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective no later than return to power from the next ;old shutdown.
FOR THE NUCLEAR REGULATORY COMMISSION q
! HLd/Wdd -
A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 6,1979 1084 254
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'o UNITED STATES 8\\
NUCLEAR REGULATORY COMMISSION
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VIRGINIA ELECTRIC AND POWER COM3ANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Anendment No. 51 License No. DPR-37 1.
The Nuclear Regulator Commission (the Commission) has found that:
A.
The application for amendnent by Virginia Electric and Power Conpany (the licensee) dated August 8,1979, complies with the standards and requirenents of the A+.omic Energy Act of 1954, as anended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confornity with the application, the provisions of the Act, and the rules and regulations of the Conmission; C.
There is reasonable assurance (i) that the activities authorized by this anendnent can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in conpiiance with the Connission'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 Connission's regulations and all applicable requirements have been satisfied.
,1084 255
_2_
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to the license anendment, and paragraph 3.B of Facility Operating License No. DPR-37 is amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 51, 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 C0tiMISSION
?k/CigWSdt-I A. Schwencer, Chief Operati.ig Reactors Branch #1 Division of Operating Reactors
Attachment:
Changes to the Technical Specifications Date of Issuance: September 6,1979 1084 2$6
ATTACHMENT TO LICENSE AMENDMENT NOS. 52 AND 51 FACILITY OPERATING LICENSE NOS. DPP.-32 AND DPR-37 DOCKET NOS. 50-280 AND 50-281 Replace the following pages of the Appendix "A" Tcchnical Specifications with the enclosed pages, The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Insert 3.7-4
- 3. 7-4 3.7-6 3.7-6 3.7-11 3.7-11 3.7-13 3.7-13 1084 257 7 $1'O{13 08 IO 0vV vv O
TS 3.7-4 P0000RGINAL to generator signals actuating the SIS active phase.
The SIS active phase is also actuated by a high containment pressure signal brought about by lost of high enthalpy coolant to the containment.. This actuation signal acts as a backup to the low pressurizer pressure actuation of the SIS and also adds diversity to protection against loss of coolant.
Signals are also provided to actuate the S,IS upon sensing the ef fects of a steam line break accident. Therefore, SIS actuation following a steam line break is designed to occur upcn sensing high differeni.ial steam presst.re between the steam heade.. and steam generator line or upon sensing high steam line flow in coincidence with low reactor coolant average teeperaturr or low steam line pressure.
The increase in the extraction of RCS heat following a steam line break results in reactor coolant temperature and pressure reduction. For this reason protection against a steam line break accident is also provided by low pres-surizer pressure actuating safety injection.
Protection is also provided for a steam line break in the* containment by actuation of SIS upcn sensing high containment pressure.
SIS actuation injects highly borated fluid into the Reactor Coolant System in order to counter the reactivity insertion brought about by cooldown of the reactor coolant which occurs during a steam line break accidcat.
Amendment No. 52 Unit 1 Amendment No. 51 Unit 2
TS 3.7-6 in order to prevent excessive cooldown of the reactor coolant system. This mitigates the effect of an accident such as stean break which in itself causes excessive coolant temperature cooldown.
Feedwater line isolation also reduces the consequences of a steam line break inside the containment, by stopping the entry of feedwater.
Setting Limits 1.
The high containment pressure limit is set at about 10% of design containment pressure. Initiation of Safety Injection protects against loss of coolant
} or steam line break accidents as discussed in the safrty analysis.
2.
The high-high containment pressure limit is set at about 50% of design containment pressure. Initiation of Contain=ent Spray and Steam Line 1 solation 1.rotects against large loss of coolant (2) or steam line break accidents ( ) as discussed in the saf ty analysis.
3.
The pressurizer icw pressure setpoint for saf ety inj ection actuation is substantially below system operating pressure limits. However, it is set suf ficiently high to protect against a loss-of-coolant accident as shown in the safety analysis.
4.
The steam line high dif ferential pressure limit is set well below Amendment No.52 Unit 1 Amendment No.51 Unit 2 1084 259
k TABLE 3.7-2 ENGINEERED SAFECUrtRDS ACTION 1
2 3
4 OPEPATOP. ACTION
!!IN.
LF CONDITIONS OF DEGREE COLUltN 1 OR 2 MIN.
OF EXCEPT AS CONDI-OPERABLE REDUN-PERMISSIBLE BYP.-
T10NED BY COLUt?! 3 FUNCTION AL LHIT CllANNELS DANCY CONDITIONS CANNOT BE flET 1 SAFETY ltuECTION a.
Manual 1
0 Cnid Shutdown b.
liigh Containment Pressure 3
1 cold Shutdown (111 Setpoint) liigh Dif ferential Pressure 2/non-1/non-c.
between any Steam Line and isolated isolated Cold Shutdown the Steam Line ficader loop loop d-Pressu rize r 1.ow 1.ow. Pressure 2
1 Primary Pressure' Cold Shutdown less than 2000 psig except when reactor is critical liigh Steam Flow in 2/3 1/steomline Reactor Coolant avor-Cold f.hutdown e.
Steam Lines with Low T 2T signals 1
age temperature less 2 S$$m Pres-1 than 547"F during or I.ow Steam Line PressNe sure Signals heatup and cooluawn.
C CD A
2 CONTAINMENT SPRAY Manual 2
Cold Shutdown t
a.
y O
b.
lligh Containment Pressure 3
1-rold Shutdown h
(Ili 111 Setpoint)
- - Must actuate 2 switches simultaneously
- - With the specified minimum operable channels the 2/3 high steam flow in already in the trip mode Amendment No. 52 Unit 1 Amendment No. 51 Unit 2
P00R ORGINAL
~
TA15LE
't 7-4 ENGINEERED SAFETY FEATURE SYSTEM INITIATION LIMITS INSTRUMENT SETTING NO.
FUNCTIONAL UNIT Cl(ANNEL ACTIOJ!
S_!'TTING LIMIT
_5 psig 1
liigh Containment Pressure (High a) Safety Injection Containment Pressure Signal) b) Containment Vacuum Pump Trip c) liigh Pressure Containment Isolation d) Safety Injection Containment Isolation e) F.W. Line Isolation
_25 psig 2
High Iligh Containment Pre s sut e - (Iligh a) Containment spray fligh Containment Pressure Signal) b) Recirculation Spray c) Steam Line Isolation d) Illgh liigh Pressure Con-tainment Isolation 1,700 psig 1
3 Pressurizer Low Low Pressure a) Safety Injection b) Safety Injection Contain-ment Isola tion c) Feedwater Line Isolation 4
liigh Dif forential Pressure Between a) Safety Injection
<t50 psi Steam 1.ine and the Steam Line lleader b) Safety Injection Contain-ment Isolation c) F.W. Line Isolation 5
liigh Steam Flow in 2/3 Steam Lines a) Safety Injection
"<40% (at zero load) of
~
full steam flow a
C
<40% (at 20% load) of F[
full steam flow b) Steam Line Isolation
$ 10% (at full load) of C
1 g
c) Safety Injection Contain-y ment Isalution full stcom flow d) F.W. Line Isolation 0
Coincident with Low T,yg or Low Steam 1541 F Tavg 1500 psig steam line Line Pressure pressure Amendment No. 52 Unit 1 Amendment No. 51 Unit 2