ML20247K534
| ML20247K534 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/24/1989 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247K542 | List: |
| References | |
| NUDOCS 8906010321 | |
| Download: ML20247K534 (35) | |
Text
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d UNITED STATES c
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20656 t
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May 24, 1989 VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No;128 License No. DPR-32 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated February 14, 1979, as supplemented September 21, 1982, August 30,1985, April 11,1988 and May 12, 1989, Act of 1954, as amended (the Act) quirements of the Atomic Energy complies with the standards and re 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 Consission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted withe-endangering the health and safety of the public, and (ii) that :,vch activities will be conducted in compliance with the Consission'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 Cosmission'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 amendnent, and paragraph 3.B of Facility Operating License No. DPR-32 is hereby amended to read as follows:
O e
"8906010321 890524 PDR ADOCK 0500C280 P
4 e-l 1
.i c-1 (B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.128. are hereby incorporated in the license. The licensee shall I
operate the facility in accordance with the Technical L
Specifications.
3.
This license amenenent is effective as of the date of its issuance.
l F
E NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate II-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the -Technical Specifications
' Date of Issuance: May 24,1989 O
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k UNITED STATES g
g NUCLEAR REGULATORY COMMISSION J
j WASHINGTON, D. C. 20555 j
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 l
SURRY POWER STATION, UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE l
Amendment No. 128 License No. DPR-37 1.-
The Nuclear Regulatory Commission (the Connission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated February 14, 1979, as supplemented September 21, 1982, August 30, 1985, April 11, 1988 and May 12, 1989, Act of 1954, as amended (the Act) quirements of the Atomic Energy complies with the standards and re 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 Connission; 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 (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 3.B of Facility Operating License No. DPR-37 is hereby amended to read as follows:
O e
(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.128, 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 He bert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects-I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the. Technical Specifications Date of Issuance: May 24,1989 t
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l
ATTACHMENT TO LICENSE AMENDMENT AMINOMENTNO.'128 FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. -128 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 ReviseAppendi$Aasfollows:
Remove Pages Insert Pages T5 ii T5 ii TS iii TS iii TS 3.1-4 TS 3.1-4 TS 3.6-1
.TS 3.6-1 TS 3.6-2 TS 3.6-2
.TS 3.6-7 TS 4.0-1 TS 4.0-1 TS 4.0-2 TS 4.0-3 TS 4.0-4 TS 4.1-9b TS 4.1-9b TS 4.1-11 TS 4.1-11 TS 4.1-12 TS 4.1-12 TS 4.2-1 TS 4.2-1 TS 4.2-2 TS 4.2-2 TS 4.2-3 TS 4.2-3 TS 4.2-4 TS 4.2-4 TS 4.2-5 TS 4.2-5 TS 4.2-6 TS 4.2-6 TS 4.2-7 TS 4.2-7 TS 4.2-8 TS 4.2-8 TS 4.3-1 TS 4.3-1 TS 4.3-2 TS 4.3-2 TS 4.3-3 TS 4.3-3 TS 4.3-4 TS 4.5-1 TS 4.5-1 TS 4.5-2 TS 4.5-2 TS 4.5-3 TS 4.5-3 TS 4.5-4 TS 4.5-4 TS 4.5-5 TS 4.5-6 TS 4.11-1 TS 4.11-1 TS 4.11-2 TS 4.11-2
TS 11
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TECHNICAL SPECIFICATION TABLE OF CONTENTS o
SECTION M
PfAg 3.15 CONTAINMENT VACUUM SYSTEM TS 3.15-1 3.16 EMERGENCY POWER SYSTEM TS 3.16-1 3.17 LOOP STOP VALVE OPERATION TS 3.17-1 3.18 MOVABLE INCORE INSTRUMENTATION TS 3.18-1 3.19 MAIN CONTROL ROOM BOTTLED AIR SYSTEM TS 3.19-1 3.20 SHOCK SUPPRESSORS (SNUBBERS)
TS 3.20-1 3.21 FIRE PROTECTION FEATURES TS 3.21-1 3.22 AUXILIARY VENTILATION EXHAUST FILTER TRAINS TS 3.22-1 3.23 CONTROL AND RELAY ROOM VENTILATION SUPPLY FILTER TRAINS TS 3.23-1 4.0 SURVEILLANCE REQUIREMENTS TS 4.0-1 4.1 OPERATIONAL SAFETY REVIEW TS 4.1-1 4.2 AUGMENTED INSPECTIONS TS 4.2-1 4.3 ASME CODE CLASS 1, 2, AND 3 SYSTEM PRESSURE TESTS TS 4.3-1 4.4 CONTAINMENT TESTS TS 4.4-1 4.5 SPRAY SYSTEMS TESTS TS 4.5-1 4.6 EMERGENCY POWER SYSTEM PERIODIC TESflNG TS 4.6-1 4.7 MAIN STEAM LINE TRIP VALVE TS 4.7-1 4.8 AUXILIARY FEEDWATER SYSTEM TS 4.8-1 4.9 EFFLUENT SAMPLING AND RADIATION MONITORING SYSTEM TS 4.9-1 4.10 REACTIVITY ANOMALIES TS 4.10-1 4.11 SAFETY INJECTION SYSTEM TESTS TS 4.11-1 4.12 VENTILATION FILTER TESTS TS 4.12-1 4.13 DEL'ETED 4.14 DELETED Amandment :;os. 128 and 128 i
TS 111 TECHNICAL SPECIFICATION TABLE OF CONTENTS SECTION TJTL[
E8gi 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY TS 4.15-1 LINES OUTSIDE OF CONTAINMENT 4.16 LEAKAGE TESTING OF MISCELLANEOUS RADIOACTIVE MATERIALS TS 4.16-1 SOURCES 4.17 SHOCK SUPPRESSORS (SNUB 8ERS)
TS 4.17-1 4.18 FIRE DETECTION AND PROTECTION SYSTEM SURVEILLANCE TS 4.18-1 4.19 STEAM GENERATOR INSERVICE INSPECTION TS 4.19-1 4.20 CONTROL ROOM AIR FILTRATION SYSTEM TS 4.20-1 5.0 DESIGN FEATURES TS 5.1-1 5.1 SITE TS 5.1-1 5.2 CONTAINMENT TS 5.2-1 5.3 REACTOR TS'5.3-1 5.4 FUEL STORAGE TS 5.4-1 6.0 ADMINISTRATIVE CONTROLS TS'6.1-l' 6.1 ORGANIZATION, SAFETY AND OPERATION REVIEW TS 6.1 1 6.2 GENERAL NOTIFICATION AND REPORTING REQUIREMENTS TS 6.2-1 6.3 ACTION TO BE TAKEN IF A SAFETY LIMIT IS EXCEEDED TS 6.3-1 6.4 UNIT OPERATING PROCEDURES TS 6.4-1 STATION 'PERATING RECORDS TS 6.5-1 6.5 O
6.6 STATION REPORTING REQUIREMENTS TS 6.6-1 6.7 ENVIRONMENTAL QUALIFICATIONS TS 6.7-1 6.8 PROCESS CONTROL PROGRAM AND OFFSITE DOSE TS 6.8-1 CALCULATION MANUAL 6.9 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS TS 6.9-1 AND SOLID WASTE TREATMENT SYSTEMS Amendment Nos.128 and 128
TS 3.1-4 J
b.
Thre's valves shall-be operable when the reactor coolant average 3
^
temperature is greater than 350*F, the reactor is critical, or i
the -Reactor Coolant System is not connected
- to the Residual Heat Removal System.
j
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c.
Valve lift settings shall be maintained at 2485 psig 1-percent.
- l 4.
Reactor Coolant Loops Loop stop valves shall not be closed in more than one loop ' unless the Reactor Coolant System is connected to the Residual Heat Removal System.and the Residual Heat Removal System is ' operable.
5.
Pre'ssurizer a.
The reactor shall be maintained suberitical by at least.1%-
until the steam bubble is established and the necessary sprays and at least 125 KW of heaters are operable.
b.
With the pressurizer inoperable due to inoperable pressurizer heaters, restore the inoperable heaters within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the reactor coolant system temperature and pressure less than 350*F and 450 psig, respectively, within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1 l
The lift setting pressure shall correspond to ambient conditions of the s
valve at nominal operating temperature and pressure.
Amendment Mos.133 and 128
T TS 3.6-1 3.6 TURBINE CYCLE Anolicability
' Applies to the operating. status of the Main Steam and Auxiliary Feed Systems.
Obiective To define the conditions required in the Main Steam ' System and Auxiliary Feed System for protection of the steam generator and' to assure the capability to remove residual heat from the core during a loss of station power.
Specification A.
A unit's Reactor Coolant System temperature or pressure shall not exceed 350*F or 450 psig, respectively, or the reactor shall not be critical unless the five main steam line code safety valves associated with each steam generator in unisolated reactor coolant loops are ope'rable with lift setting as specified in Table 3.6-1A' and 3.6-18.
8.
To assure residual heat removal capabilities, the folloudng conditions shall be met prior to the consnencement of any unit operation that would establisn reactor coolant system conditions of 350*F and 450 psig which would preclude operation of the Residual Heat Removal System.
1.
Two motor driven auxiliary feedwater pumps shall be l
operable, and one of three auxiliary feedwater pumps for
[
the opposite unit shall be available.*
b Available means (1) operable except for automatic initiation instrumentation, (2) offsite or emergency power source may be inoperable in cold shutdown, and (3) it is capable of being used with the opening of the cross-connect.
Amendment Nos.128 and 128
~*-
. o TS 3.6-2 2.
A minimum of 96,000 gallons of water shall be available in
.the tornado missile protected condensate storage tank to supply emergency water to the auxiliary feedwater pump suctions.
A minimum of -60,000 gallons of water shall be available in the torn' ado protected condensate storage tank of the opposite unit to supply emergency water to the auxiliary feedwater pump suction of that unit.
3.
All main steam line code safety valves, associated with steam generators in unisolated reactor coolant loops, shall be operable with lift setting as specified in Table 3.6-1A and 3.6-1B.
C.
Prior to reactor power exceeding 107,,
the steam driven auxiliary feedwater pump shall be operable.
I 0.
System piping, valves, and control board indication required for the operation of the components enumerated in Specifications 3.6.B.1, 3.6.B.2, 3.6.8.3, and 3.6.C shall be operable with the system piping, valves, and control board indication required for the operhtion of the opposite unit auxiliary feedwater pump available.*
E.
The iodine - 131 activity in the secondary side of any steam generator, in an unisolated -reactor coolant loop, shall not exceed 9 curies.
Also, the specific activity of the secondary I
coolant system shall be s 0.10 uti/cc DOSE EQUIVALENT I-131.
t If the specific activity of the secondary coolant system exceeds 0.10 gCi/cc DOSE EQUIVALENT I-131, the reactor shall be shut down and cooled to 500*F or less within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after detection and in the cold shutdown condition within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i Available means (1) operable except for automatic initiation
{
instrumentation, (2) offsite or emergency power source may be inoperable in cold shutdown, and (3) it is capable of being used with the opening of the cross-connect.
)
Amendment Mos.128 and 128
TABLE 3.6-1A UNIT 1 MAIN STEAM SAFETY VALVE LIFT SETTING i
i VALVE NUMBER LIFT SETTING *f ORIFICE SIZE SV-MS-101A, B, C 1085 psig 7.07 sq. in.
SV-MS-102A, B, C 1095 psig 16 sq. in.
SV-MS-103A, B, C 1110 psig 16 sq. in.
SV-MS-104A, B, C 1120 psig 16 sq. in.
SV-MS-105A, B, C 1135 psig 16 sq. in.
TABLE 3.6-1B UNIT 2 MAIN STEAM SAFETY VALVE LIFT SETTING VALVE NUMBER LIFT SETTING *#
ORIFICESk2E SV-MS-201A, B, C 1085 psig 7.07 sq. in.
SV-MS-202A, B, C 1095 psig 16 sq. in.
SV-MS-203A, B, C 1110 psig 16 sq. in.
SV-MS-204A, B, C 1120 psig 16 sq. in.
SV-MS-205A, B, C 1135 psig 16 sq. in.
The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
The as found condition shall be 3% and the as left condition shall be 1%.
Amendment Nos. 128 and 128
TS 4.0-1
)
4.0 SURVEILLANCE REQUIREMENTS
.0.1 Su'rveillance Requirements provide for
- testing, calibrating, or inspecting those systems or components 1
which are required to assure that operation of the units
-f or the station will be as prescribed in the preceding 1
sections.
4.0.2 Surveillance Requirement specifled time intervals may be adjusted plus or minus 25 percent. to accommodate normal test schedules.
4.0.3 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 3 coniponents shall be applicable as follows:
a.
Inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1,
2., and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and l
Pressure Vessel Code and applicable Addenda as l
required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
b.
Surve,111ance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be appli-cable as follows in these Technical Specifications:
I l
Amendment Mos. 128 and 128
TS 4.0-2 4
ASME Boiler and Press 0re Vessel Code and Applicable Required Frequencies Addenda Terminology for for Performing Inservice Inspection and Inservice Inspection Testina Activities and Testina Act'vities Monthly At least once per 31 days Quarterly or Every 3 Months At least once per 92 days Cold Shutdown At least once per CSD Refueling Shutdown At least once per RSD c.
The provisions of Specification 4.0.2 are applicable to the above required frequencies for pump and valve testing only.
Extensions for inservice inspection of components will be to the requirements of Section XI of the ASME Boiler and Pressure Vessel Code.
d.
Performance of the above inservice inspection and testing activities shall be in addition to other specified Surveillance Requirements.
e.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
r Amendment Nos.128 and 128 4
__.m_-.-.___
O TS 4.0-3 This specification provides that surveillance activities necessary to
' insure the Limiting Conditions for Operation are met and will be performed during all operating conditions for which the Limiting Conditions for Operation are applicable.
The provisions of this specification provide allowable tolerances for performing surveillance activities beyond those. specified in the nominal surveillance interval.
These tolerances are necessary to provide operational flexibility because of scheduling and performance con-siderations.
The phrase "at least" associated with a surveillance frequency does not negate this allowable tolerance value and permits the performance of more frequent surveillance activities.
This specification ensures that inservice inspection,
- repairs, and replacements of ASME Code Class 1, 2, and 3 components and inservice testing of ASME C' ode Class 1, 2, and 3 pumps and valves will be performed in accordance with a periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a.
Specific relief from portions of the above requirements has been provided in writing by the Commission and is not a part of these Technical Specifications.
This specification includes a clarification of the frequencies for performing the inservice inspection and testing activities required by Sect ~ ion XI' of the ASME Boiler and Pressure Vessel Code and applicable Addenda.
This clarification is provided to ensure consistency in surveillance intervals throughout these Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.
i Amendment Nos. 128 and 128
TS 4.0 4 Under the terms of this specification, the more restrictive requirements of 'the Technical Specifications take precedence over the ASME Boiler and Pressure 'Ve'ssel Code and applicable Addenda.
For example, the Technical Specification definition of operable does not grant a grace period before a device that is not capable of. performing its specified. function is declared inoperable and takes precedence over the ASME Boiler and Pressure Ves. eel Code' provision which allows a valve to be incapable of
- erforming its specified function for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before being declared inoperable.
l Amendment Mos. 128 and 123 4
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l 4.2 AUGMENTED INSPECTIONS Acolicability Applies to inservice inspections wt.ich augment those required by ASME Section XI.
)
Ob.fective To provide the additional assurance necessary for the continued-integrity of important components involved in safety and plant operation.
Soeci fic,311'Il A.
Inspections ' shall be performed as specified in T.S.
Table 4.2-1.
Nondestructive examination techniques and acceptance criteria shall ~be in compliance with the requirements of TS 4.0.3.
B.
The normal inspection interval is 10 years.
C.
Detailed records of each inspection shall be maintained to allow a continuing evaluation and comparison with future inspections.
IAlti The inspection. program for ASME Section XI of the ASME Boiler and Pressure Vessel Code limits its inspection to ASME Code Class 1, 2, and 3
components and supports.
Certain components, under Miscellaneous Inspections in this section, were added because of no corresponding code requirement.
This added requirement provides the inspection necessary to insure the continued integrity of these
)
components.
Amendment
- os.128 and 128
.TS 4.2-2'
~4 Sonsitized. stainless steel augmented inspections were added to
- assure piping integrity of this classification.
Item 2.1-ASME Class I sensitized stainless steel piping will be inspected at three times the frequency required by the Code.
Visual inspections will be conducted, while the piping is pressurized by the' procedures defined in Table 4.1-3 of Technical Specification' 4.1 concerning flushing of sensitized stainless steel piping.
Item 2.2 Sensitized stainless steel piping designated ASME Class 2 or not subject to section XI of the ASME Code, will undergo visual and.
surface. examination.
The containment and recireciation spray rings, which are located' in the overhead of the containment, will be visually inspected.
-Additionally, sections of the piping _ will be examined by liquid penetrant inspection when the piping is visually inspected.
At
. least 25 percent of the examinations shall have been completed. by the expiration of one-third of the inspection interval and at least 50 percent shall have been completed by the expiration of two-thirds of the inspection interval.
The remaining examinations shall be completed by the enu of the inspection interval.
l.
All other piping included in Item 2.2 will be visually inspected at least every two years.
Sections of this piping will be examined by liquid penetrant inspection when the piping is visually inspected.
For the required visual inspection, the piping will be pressurized by the procedures defined in Table 4.1-3 of Technical. Specification 4.1 concerning flushing of sensitized stainless steel piping.
Amendment Nos.128 and 128 4
_.____.m.__
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1 Amendment Nos.128 and 128
TS 4.3-1
~ 4.3 ASME CODE CLASS 1, 2,-AND 3 SYSTEM PRESSURE TESTS Aeolicability Applies to requirement for ASME Code Class 1, 2,
and 3 System Pressure Tests.
In this context, closed is ' defined as -the state of system integrity which permits pressurization and subs'equent normal operation after the system has been opened.
Obiective To - specify requirements for ASME Code Class 1, 2, and 3 System Pressure Tests following normal operation, modification, or repair.
The' pressure-temperature limits for Reactor Coolant System tests will be in accordance with Figure 3.1-1.
Specification A.
Inservice inspection, which includes system pressure testing, of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10. CFR 50,
.Section 50.55a(g), except where specific written relief has.
.been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).
8.
Each time the Reactor Coolant System is closed, the system will be leak tested at a test pressure of not less than the nominal operating
-pressure
+100 psi in conformance with NOT retirements.
Amendment Nos.128 and128
l L
-s TS 4.3-2 E8111t l
l System pressure testing is performed in order to insure integrity of the 1
j.
system.
For normal opening the integrity of the system, in terms of strength, i's unchanged.
If, for example, the Reactor Coolant System does not leak at the nominal operating pressure plus 100 psi, it will be assumed leaktight for normal operation.
The testing is based on 10 CFR 50.55a and performed pursuant to Section XI of the ASME Code for inservice inspection of Class 1,
2, and 3 components.
l l
Amendment Nos.128 and 128 l
TS 4.3-3 0
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(Pages TS 4.3 3 and TS 4.3-4 have been deleted) l l
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Amendment Nos.128 and 128
TS 4 5 1 4.5 SPRA'Y SYSTEMS TESTS Aeolicability Applies to the testing of the Spray Systems.
l.
Obiective, To verify that the Spray Systems will respond promptly and perform.their -
design function, if required.
Specification A.
Each containment spray subsystem shall be demonstrated operable:
.l.
By. verifying, that on recirculation flow, each containment spray pump performs satisfactorily when tested in accordance with Specification 4.0.3.
2.
By verifying that each motor-operated valve in the containment spray flow path performs satisfactorily-when tested in accordance with Specification 4.0.3.
3.
At least once par 5 years, coincident with the closest refueling outage, by performing an air or smoke flow test and-verifying each spray nozzle is unobstructed.
~
4.
Coincident with the containment spray pump test described in Specification 4.5.A.1, by verifying that no particulate material clogs the test spray nozzles in the refueling water storage tank.
B.
Each recirculation spray subsystem shall be demonstrated operable:
1.
By verifying each recirculation spray pump performs satisfactorily when tested in accordance with Specification 4.0'.3.*
Except that each inside containment recirculation spray pump sha.ll be dry tested at least once per month.
The dry test of a recirculation spray pump shall be considered satisfactory if the motor and pump shaft rotates, starts on signal, and the ammeter readings for the motor are comparable to the original dry test ammeter readings.
Amendment Nos.128 and 128
_u
TS 4.5-2
.\\
~
2.
By verifying that each motor operated valve in the recirculation spray flow paths performs satisfactorily when tested in accordance with Specification 4.0.3.
3.
At least once per 5 years, coincident with the closest refueling outage, by performirg on air or smoke flow test and verifying each spray nozzle is unobstructed.
C.
Each weight-loaded check valve in the containment spray and outside containment recirculation spray subsystems shall be demonstrated
~
operable at least once per 18 months, during shutdown, by cycling the valve one complete cycle of full travel and verifying that each valve opens when the discharge line of the pump is pressurized with air and seats when a vacuum is app. lied.
HA111 The flow testing of each containment spray pump is performed by opening the normally closed valve in the containment spray pump recirculation line returning water to the refueling water storage tank.
The containment spray pump is operated aad a quantity of water recirculated to the refueling water storage tank.
The discharge to the tank is divided into two fractions; one for the major portion of the recirculation flow and the other to pass a small quantity of water through test nozzles which are identical with those used in the containment spray headers.
The purpose of the recirculation through the test nozzles is to assure that there are no particulate material in the refueling water storage tank small enough to pass through pump suction strainers and large enough to clog spray nozzles.
Due to the physical arrangement of the recirculation spray pumps inside the containment, it is impractical to flow-test them periodically.
These pumps are cipable of being operated dry for 60 seconds and it can be determined that the pump shafts are turning by rotation sensors which indicate in the Main Amendment Nos. 128 and 128 l
TS 4.5-3 1
.*~
Control Room.
Motor current is indictted on an ammeter in the Control Room,
{
and will.be compared with, readings recorded during preoperational tests to ascertain that no degradation of pump operation has occurred.
The recirculation spray pumps outside the containment have the capability of being dry-run and flow tested.
The test of an outside recirculation spray pump is performed by closing the suction line valve and the isolation valve between
~
the pump discharge and the containment penetration.
This ' allows the pump casing to be filled with water and the pump to recirculate water through a test line from the pump dische.rge to the pump casing.
With a system flush conducted to remove particulate matter prior to the installation of spray nozzles and with corrosion resistant nozzles and piping, it is not considered credible that a significant number of nozzles would plug during the life of the unit to reduce the effectiveness of the subsystems; therefore provisions to air-test the nozzles every 5 years, coinciding with the closest refueling outage, is suff f ent to indicate that plugging of the nozzles has not occurred.
The spray nozzles in the refueling water storage tank provide means to ensure that there is no particulate matter in the refueling water storage t:.nk and the containment spray subsystems which could plug or cause deterioration of the spray nozzles.
The nozzles in the tank are identical to those used on the containment spray headers.
l j.
Tite flow test of the containment spray pumps and recirculation to the refueling water storage will indicate any plugging of the nozzles by a reduction of flow through the nozzles.
REFERENCES FSAR Section 6.3.1, Containment Spray Pumps FSAR Section 6.3.1, Recirculation Spray Pumps l
Amendment Hos. 128 and 128
-m_.____O
TS 4.5-4 t
L-4 1
(Pages TS 4.5-4, TS 4.5-5, and TS 4.5-6 have been deleted)
Amendment Mos. IT'>
and 128
TS 4.11 !
L 4~.11-SAFETY INJECTION SYSTEM TESTS Ao cability l
Applies to operational testing of the Safety injection System.
Obiactive To verify that the Safety Injection System will respond promptly and perform its design functions, if required.
Specification A.
The safety injection system shall be demonstrated operable:
- 1..
By verifying, that on recirculation flow, each low head safety injection pump performs satisfactorily when tested in accordance with Specification 4.0.3.
2.
By verifying, that on recirculation flow, each charging pump performs satisfactorily when tested in accordance with Specification 4.0.3.
3.
By verifying that each motor-operated valve in the safety i
injection flow path performs satisfactorily when tested in accordance with Specification 4.0.3 4.
At least once per 18 months, during shutdown, by:
~
a.
Verifying that each automatic valve in the flow path l
actuates to its correct position on a safety injection j
test signal.
The charging and low head safety injection pumps may be immobilized for this test.
b.
Verifying that each of the charging and safety injection pump circuit breakers actuate to its correct position on a l
safety injection test signal.
The charging and low head l
safety injection pumps may be immobilized for this test.
Amendment Nos. 128 and 128
-3 TS 4.11-2 l
~
M Complete system tests cannot be performed when the reactor is operating because a safety injection signal causes containment isolation.
The method of I
assuring operability of these systems is therefore to combine system tests to be performed during refueling shutdowns, with more frequent component tests, which can be performed during reactor operation.
The system tests demonstrate proper automatic operation of the Safety Injection System.
k test signal is applied to initiate automatic operation action and verification is made that the components receive the safety injection signal in the proper sequence.
The test may be performed with the pumps blocked from starting.
The test demonstrates the operation of the valves, pump circuit breakers, and automatic circuitry.
During reactor operation, the instr'imentation which is depended on to initiate safety injection is checked periodically, and the initiating circuits are tested in accordance with Specification 4.1.
In addition, the active' components (pumps and valves) are to be periodically tested to check the operation of the starting circuits and to verify that the pumps are in satisfactory running order.
The test interval is determined in accordance with ASME Section XI.
The accumulators are a passive safeguard.
In accordance with Specification 4.1, the water volume and pressure in the
' accumulators are checked periodically.
Reference FSAR Section 6.2, Safety Injection System Amendment Nos'.128 and 128
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