ML20066C878
| ML20066C878 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/28/1990 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066C880 | List: |
| References | |
| NUDOCS 9101110275 | |
| Download: ML20066C878 (12) | |
Text
-.
1
[>3 880 9
UNITED STATES g1 g
NUCLEAR REGULATORY COMMISSION WASHING TON, D, C. 20555
/
December 28, 1990 a
%,,...../
}
VIRGINIA ELECTRIC AND POWER _ COMPANY-I DOCKET NO. 50-280 SURRY POWER _ STATION, UNIT N0_. 1~
[
AMENDMENT _T0 FACILITY OPERATING LICENSE Amendment No. 150 l
License No. OPR-32 1.
The Nuclear Regulatory Comission (the Comission) has'found that:-
A.
The application for amendment by Virginia Electric and Power-Company (the licensee) dated March 8, 1990, 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 conformity with the application,-
the provisions of the Act, and the rules and regulations of-the Comission; C.
Thereisreasonableassurance(i)thatthe-activitiesauthorized=
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 Comission's regulations; D.
The issuance of this-amendment will not be inimical to the comon 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 Comission'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 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
9101110275 901228..
PDR ADOCK 05000280; P
PDR.
l
a 4 December 28, 1990 (B) Technical Specifi_ cations The Technical Specifications contained in Appendix A, as revised through Amendment No.150, are hereby incorporated in the license.1 The. licensee-shall operate the facility in accordance~with the-Technical Specifications.
3.
This license amendment is effective at of the date of.its issuance..
FOR THE NUCLEAR' REGULATORY COMMISSION
/
h, Director &
a bert H. Ber roject Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 28, 1990 i
l l
l
, s uc,
ua f.
.g UNITED STATES
( ' > eq j
NUCLLAR REGULATORY COMMISSION
- r. -
wAsmNO ton. D. C. 20568 i
.f December 28, 1990 VIRGINIA _.ELECTRir AND_ POWER COMPANY DOCKET NO. 50-281 SURRY F0WER STATION,_ UNIT NO 2 AMENDMENT _T0_ FACILITY OPERATING _L_ICENSE Amendment No.147 License No. DPR-37 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated March 8, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954 amended (the Act) and the Comission's rules and regulations, as 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 Comission; C.
There is reasonable assurance (i) that the activities authorized by this amer.dment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the comon 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 Comission's regulatioits 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 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
4 sg.,.
e
,,,,e g,._
n.,,
-7,
,v.
a i
1 December 28, 1990 (B) Technica_1 Specifjeatjons The Technical Specifications contained in Appendix A, as revised through Amendment No. 147, are hereby incorporated in the license. The licensee shall t
operate the facili+y in accordance with the Technical Spec!fications.
3.
This license a.nendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Dn 1
H r ert 11. Berkow, Director-Project Directorate !!-2 Division of Reactor Projects - I/II Office of. Nuclear Reactor Regulation 4
tittachment:
Changes to the Technical Specifications Date of Issuance: December 28, 1990 f
l
ATTACHMENT _T0_ LICENSE AMENDMENT AMENDMENT NO. 150 FACILITY _ OPERATING _ LICE _NSE NO. OPR-32 AMENDMENT _NO._147
_ FACILITY OPERAT1HG LICENSE __NO. OPR-37 DOC _KET NOS._50 _280_AND_50-281 Revise Appendix A as follows:
Remove Pages Insert Pagg TS 4.1-le-TS 4.1-la TS 4.1-2
- TS 4.1-2 TS-4.1-4
- TS 4.1-4 TS-4.1-4a l
TS 4.1-5 TS 4.1-S I
TS 4.1-10 TS 4.1-10 TS 4.1-11 TS 4.1-11 TS 4.1-12 TS 4.1-12.
s
__w------_s---,
g i
TS 4.1-la 3.
The pressurizer water volume shall be determined to be within its limit as defined in Specification 2.3.A.3.a at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the reactor is not subcritical by at least 1% ak/k.
4 Each Reactor Vessel Head vent path remote operating isolation valve not required to be closed by Specification 3.1.A 7a or 3.1.A.7b shall be demonstrated operable at each cold shutdown but not more often than ont:e per 92 days by operating O't: valve thi'ough one complete cycle of full travel from the control room.
5.
Each Reactor Vessel Head vent path shall be demonstrated operable following each refueling by:
Verifying the manual isolation valves in each vent a.
path are locked in the open position, b.
Cycling each remote operating isolation valve through
^
at least one complete cycle of full travel from the control room.
Verifying flow through the reactor vessel head vent systes c.
vent paths.
C.
Sampling tests shall be conducted as detailed in Table 4.125.
D.
Whenever containment intetrity is not required, only the asterisked items in Table 4.1 1 and 4.1 1A and 4.1 28 are applicable.
E.
Flushing of wetted sensitized stainless steel pipe sections as identified in the Basis Section shall be conducted only if the RWST Water Cheatstry exceeds 0.15 PPM chlorides and/or fluorides (Cl*
and/or F').
Flushing shall be conducted as detailed in TS Table 4.1 3A and 4.1 38.
Amendment Nos.150 and 147.
~___ _ _____ __
TS 4.1 2 H.
If the RWST Water Chemistry exceeds 0.15 PPM for Cl* and/or F',
flushing of sensitized stainless steel piping as required by 4.1.E will be performed once the RWST Water Chemistry has been brought within specification limit of less than 0.15 PPM chlorides and/or fluorides.
Samples will be taken periodically untti the sample indicates the Cl* and/or F' and levels are below 0.15 PPM.
Baill thed Failures such as blown instrument fuses, defective indicators, and faulted amplifiers which result in
' upscale' or
'downscale' i
indication can be easily recognized by simple observation of the functioning of an instrument or system.
Furthermore, such failures are, in many cases, revealed by alans or annunciator action, and a periodic check supplements this type of built-in surveillance.
Based on experience in operation of both conventional and nuclear unit systems, when the unit is in operation, the minimum checking frequencies set forth are deemed adequate for reactor and steam system instrumentation.
Calibration Calibration shall be performed to ensure the presentation and acquisition of accurate information.
The nuclear flux (power level) channels shall be calibrated daily against a heat balance standard to account for errors induced by changing roi patterns and core physics parameters.
Amendment Nos.150 and 147,
{
TS 4.1 4 For the specified one month test interval, the average unprotected time is 360 hrs in case of a failure occurring between test intervals.
Thus, the probability of failure of one channel between test intervals is 360 x 2.5 x 10-6 or.9 x 10'3 Since two channels must fail in order to negate the safety function, the probability of simultaneous failure,of two out of three channels is 3(.9 x 10-3)2, 2.4 x 10'0 This represents the fraction of time in which each three channel system would have one operable and two inoperable 10-6 channels and equals 2.4 x x 8760 hours0.101 days <br />2.433 hours <br />0.0145 weeks <br />0.00333 months <br /> per year, or (approximately) 1 minute / year.
It must also be noted that to thoroughly and correctly test a channel, the channel components must be made to respond in the same manner and to the same type of input as they would be expected to respond to during their normal operation.
This, of necessity, requires that during the test the channel be made inoperable for a short period of time.
This factor must be, and has been, taken
'o consideration in determining testing frequencies.
Because of their greater degree of redundancy, the 2/4 logic arrays provide an even greater measure of protection and are thereby acceptable for the same testing interval. Those items specified for monthly testing are associated with process components where other means of verification provide additional assurance that the channel is operable, thereby requiring less frequent testing, i
Amendment Nos.150 and 147,
l TS 4.1 4a N1uthine During construction of the facility, stress relieving of some of the cold bent stainless steel piping resulted in the piping becoming sensitized i
to potential stress corrosion cracking under certain conditions, e.g. low pH in conjunction with high chlorides.
The subsystems containing the sensitized piping.were identified in Stone
& Webster Report SW MER 1A dated July 6,1971 and further evaluated
)
t i
in Virginia Power Technical Report ME 0009, Rev. l. dated 0ecember
~
9, 1987.
The sensitized piping was either not wetted, reheat treated, or is justified as acceptable because it is in a wetted system with adequate chemistry control i.e.,
chlorides and/or fluorides (Cl* and/or F*) less than 0.15 ppe.
These subsystems are as follows:
Subsyntag 1
Recire, spray inside containment Egggkg i
- 2) Rectre, spray outside containment
)
Not Wetted.
t Not Wetted
- 3) Containment spray outside containment Containment spray inside containment Not Wetted 4)))
1 Wr.cted 5
Low hd. $1 pump discharge
'atted 6
Low hd. SI pump to ist iso valve Wetted 7 ) Hi h hd. SI inside containment Wetted 8h Hi h hd. SI pump discharge Wetted i
91 RH Wetted 101 Charging and letdown system in containment Flowing System 11)
Pressurizer relief lines Reheat Treated Prior to Operation 12)
Pressurizer spray & surge lines Flowing System The sensitized piping found in a wetted system is acceptable as long I
as the fluid in or passing through th).91 ping is less than 0.15 PPM C1' and/or F'.
The wetted systems are supplied from tho'RWST with the exception of the RHR system which communicates directly with the RCS during _ plant shutdowns.
The RHR systes does not communicate with the RWST during power operations and - therefore, does not require flushing if Cl* and/or F' concentration exceeds ' 0.15 ppe.
The acceptance criteria for the piping are based on the RWST Water chemistry staying below 0.15 PPM chlorides and/or fluorides.- If the RWST chemistry on chlorides and/or fluorides is~out of specification the sensitized piping that is nomally supplied by-the RWST will be i
flushed pet tables 4.13A and 4.1-38 for Units 1 and 2 respectively.
Each refueling outage the wetted systems are flow tested,or put in service which will flush the strategic portions of those systems, i
Amendment Nos. 150_and 147.
i
. ~
~
. s'
T3 4.1 5 The refueling water storage tank is sempled weekly for Cl* and/or F*
contaminations.
Weekly sampling is adequate to detect any inleakage of contaminated water.
The control room ventilation system is required to establish a positive differential pressure in the control room for one hour following a design basis luss-of coolant accident using a bottled air supply as the source of air.
The ability of the system to meet this requirement is tested by pressurizing the control room using the ventilation system fans and comparing the volume of air required to that stored.
The test is conducted each refueling interval (approximately 12 to 18 months), nonna11y coinciding with the refueling outage of either Unit 1 or Unit 2.
l Amendment Nos.150 and 147
TS 4.1 10 TABLE 4.1-2R MINIMUM FREQUENCIES FOR SAMPLING TESTS EIAB DESCPRIPTION If,il, FREQUENCY REFtRENCE SECTON 1.
Reactor Coolant Liquid Radio Ch cal Monthly (5)
Samples Analysisg<
GrossActivity(2) 5 days / week (5I 9.1 Tritius Activity "
Weekly (5) 9.1
- Chemistry
- BoronConce(ntrationCL, F & 0 ) 5 days / week4 2
E Determination Twice/ week 9.1 Sesiannually DOSE EQUIVALENT I 131 Once/2 weeks Radio-iodine Once/4 hours Analysis (includin I-and (7) below 131, 1 133 1 1 135 2.
Refueling Water Storage Boron Concentration Weekly 6
Chemistry (C1 & F)
Weekly 3.
Beic Acid Tanks
- Boron Concentration Twice/ Week 9.1 4
Chemical Additive Tank NaOH Concentration Monthly 6
5.
Spent Fuel Pit
- Boron Concentration, Monthly 9.5 6.
Secondary Coolant Fifteen sinute degassed Once/72 hours 10.3 b and q activity DOSE EQUIVALENT I-131 Monthly (4)
Semiannually (8) 7.
Stack Gas lodine and
- l 131 and particlate Weekly Particulate Samples radioactive releases 8.
Accumulator Boron Concentration Monthly 6.2
- See Specification 4.1.0 (1)
A radiochemical analysis will be made to evaluate the following corrosion products: Cr 51, Fe 59, Mn 54, Co 58, and Co 60.
(2)
A gross beta gamma degassed activity analysis shall consist of the tative measurement of the total radioactivity of the primary coolan@t in anti-units of pC1/cc.
Amendment Nos.150 and 147
4 TS 4.1 11 t
- * * - * =,,
liiiii-i
.l l
g 1
i 11111
.g
!-l le 8 i 1
~
gg f
n f
4 d
i I
jh I)
- jl!!Iallg 3
l' 1;tt!! lI I
i s
ll 13 ;11 1.11 i
aa 55 aan,a Amendment Nos.150 and 147
I i
THEX 4.1-35 unse? 2
~
Emmang pgggumary mm Firasams: sumsmrrian FIng t
i Flandt F3ctr Equtan General r-
- _.- 1, c-
, = = -
_ t ::::
m 4
Flanda e
- 1) Castalquest 4mmy Rap h_,
note 1 Note 2 l
- 2) Im Hb SI Rap nierharge Mate 1 1
Mate 2
- 3) Im H$ S1 Pump tp to let Iso.11Anlwa Note 1 Mate 2 L
t
- 4) Mig tt Hd SI Pump Inside Oostafment Note 1 Note 2 t
i i
- 5) Hispa 1*l SI Rap ni-;
_y teote 1 seats 2 r
E Beate 12 FlasAt natil semple is him 0.15 PHf C1 an4ror F'
~
-)
g I
Beate as amen seer o==nq has e o.15 syst CL an4for F- (only after Wnring the t
l E.
Her hiM to spec for C1 an4/or F )
g 4
1 j
l z
O L
h u.
o
-4 r
W en 3Q' i
7 g
one 5
e i
N w
N i
5
.