ML20202H829
| ML20202H829 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/29/1999 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | Southern Nuclear Operating Co, Georgia Power Co, Oglethorpe Power Corp, Municipal Electric Authority of Georgia, City of Dalton, GA |
| Shared Package | |
| ML20202H834 | List: |
| References | |
| NPF-68-A-105, NPF-81-A-083 NUDOCS 9902080247 | |
| Download: ML20202H829 (27) | |
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t UNITED STATES
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j NUCLEAR REGULATORY COMMISSION i
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WASHINGTON, D.C. 20666-0001 y*****j SOUTHERN NUCLEAR OPERATING COMPANY. INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA VOGTLE ELECTRIC GENERATING PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.105 License No. NPF-68
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Vogtle Electric Generating Plant, Unit 1 (the facility) Facility Operating License No. NPF-68 filed by the Southern Nuclear Operating Company, Inc. (Southem Nuclear), acting for itself, Georgia Power Company, OGLETHORPE Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated June 26,1998, as supplemented by letters dated September 18 and November 30,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 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 set forth in 10 CFR Chapter I; 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.
9902000247 990129 PDR ADOCK 05000424 P
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- 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating' License No. NPF-68 is hereby amended to read as follows:
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 105
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR T UCLEAR REGULATORY COMMISSION flL hlk kof Herbert N. Berkow, Director Project Directorate 112 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation i
Attachment:
Technical Specification Changes Date of issuance:
January 29, 1999 w
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION
- WASHINGTON, D.C. 30e06-4001
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SOUTHERN NUCLEAR OPERATING COMPANY. INC.
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L GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA l:
VOGTLE ELECTRIC GENERATING PLANT. UNITl AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. NPF-81
'1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment to the Vogtle Electric Generating Plant, Unit 2 (the facility) Facility Operating License No. NPF-81 filed by the Southern Nuclear Operating Company, Inc. (Southern Nuclear), acting for itself, Georgia Power OGLETHORPE Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated June 26,1998, as supplemented by letters dated September 18 and November 30,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission'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 Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can
< be conductf d without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; 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.
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. 2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-81 is hereby amended to read as follows:
Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 83
, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Southern Nuclear i
shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 90, Herbert N. Berkow, Director Project Directorate 112 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation
Attachment:
Technical Specification Changes Date of Issuance: January 29, 1999
ATTACHMENT TO LICENSE AMENDMENT NO. 105 FACILITY OPERATING LICENSE NO. NPF-68 DOCKET NO. 50-424 AND TO LICENSE AMENDMENT NO. 83 FACILITY OPERATING LICENSE NO. NPF-81 DOCKET NO. 50-425 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain verticallines indicating the areas of change.
1 Remove Insert 3.3-49 3.3-49 3.3-51 3.3-51 3.3-53 3.3-53 8 3.3-146 B 3.3-146 B 3.3-147 8 3.3-147 B 3.3-147a*
B 3.3-147b' B 3.3-148 B 3.3-148 8 3.3-149 B 3.3-149 B 3.3-150 B 3.3-150 B 3.3-152 B 3.3-152 3.7-15 3.7-15 3.7-16 3.7-16*
B 3.7-37 B 3.7-37 3.9-6 3.9-6 3.9-7 3.9 7 83.914 B 3.9-14 B 3.9-15 B 3.9-15 B 3.9-16 83.916 B 3.9-17 8 3.9-17 B 3.9-18 B 3.9-18 B 3.9-19 8 3.9-19
- no change overflow or blank page
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Containment Ventilation Isolation Instrumentation 3.3.6 3.3 INSTRUMENTATION 3.3.6 Containment Ventilation Isolation Instrumentation LCO 3.3.6 The Containment Ventilation Isolation instrumentation for each function in Table 3.3.6-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.6-1.
l ACTIONS
NOTE-------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Only one radiation A.1 Restore at least two 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> monitoring channel channels to OPERABLE i
status.
(continued)
Vogtle Units _1 and 2 3.3-49 Amendment No.105 (Unit 1)
Amendment No. 83 (Unit 2)
9 e
a Containment Ventilation Isolation Instrumentation 3.3.6 l
ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.
-NOTE---------
C.1 Place and maintain Immediately Only a) licable during containment puqe and CORE A. ERATIONS or exhaust valves in closed movement of irradiated position.
i fuel assemblies within containment.
QB No radiation monitoring C.2 Enter applicable Immediately l
channels OPERABLE.
Conditions and Required Actions of LC0 3.9.4, QR
" Containment Penetrations," for Required Action and containment purge supply associated Completion and exhaust isolation Time for Condition A penetrations not in not met.
required status.
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l Vogtle Units 1 and 2 3.3-51 Amendment No.105 (Unit 1) i Amendment No. 83 (Unit 2) 1
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Containment Ventilation Isolation Instrumentation 3.3.6 Table 3.3.6-1 (page 1 of 1)
Contalrunent Ventitation Isolation Instr m tation I
APPLICABLE MODES l.
OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS TRIP sETPOINT 1.
Manuel Initiation 1,2,3,4 2
SR 3.3.6.6 NA l
2.
Automatic Actuation Logic 1,2,3,4 2
sa 3.3.6.2 NA l
and Actuation Relays st 3.3.6.3 sa 3.3.6.5 3.
Contefrument Radiation 1,2,3,4,6(8) 2(*)
st 3.3.6.1 i
st 3.3.6.4 l
SR 3.3.6.7 SR 3.3.6.3 a.
Gaseous (b)
(RE 2565C) b.
Particulate (b)
(RE 2565A) c.
lodine (b)
(RE 25658) d.
Area Low Range s 15 mr/h(8)
(RE-0002, RE 0003) s 50x background (d) 4.
Safety injection 1,2,3,4 Refer to LCO 3.3.2{ "ESFAs Instrumentation,"
l F metion 1, for al initiation f mettons and requirements.
(a) Containment ventilation radiation (RE 2565) is treated as one channet and is considered OPERABLE if the particulate (RE 2565A) and lodina monitors (RE 25658) are OPERABLE or the noble ses monitor (RE 2565C) is OPERABLE.
(b) setpoints will not exceed the timits of specifications 5.5.4.h and 5.5.4.1 of the Radioactive Effluent Controls Program.
(c) During CORE ALTERAT10NS and movement of irradiated fuel assembtles within containment.
(d) During MODES 1, 2, 3, and 4.
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Vogtle Units 1 and 2 3.3-53 Amendment No. 105(Unit 1)
Amendment No. 83(Unit 2)
Containment Ventilation Isolaticn Instrumentaticn B 3.3.6 BASES (continued)
E APPLICABLE The safety analyses assume that the containment remains SAFETY ANALYSES intact with penetrations unnecessary for core cooling isolated early in the event, within approximately 1
60 seconds. The isolation of the purge supply and exhaust valves has not been analyzed mechanistically in the dose calculations, although its rapid isolation is assumed. The containment purge supply and exhaust isolation radiation monitors act as backup to the SI signal to ensure closing of the purge supply and exhaust valves for events occurring in MODES 1 through 4.
Manual isolation (using individual valve I
handswitches) following a radiation alarm is the assumed means for isolating containment in the event of a fuel 4
handling accident during shutdown. Containment isolation in turn ensures meeting the containment leakage rate a
assumptions of the safety analyses, and ensures that the i
calculated accidental offsite radiological doses are below 10 CFR 100 (Ref. 1) limits.
The containment ventilation isolation instrumentation satisfies Criterion 3 of the NRC Policy Statement.
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LCO
-The LCO requirements ensure that the instrumentation necessary to initiate Containment Ventilation Isolation, 4
i listed in Table 3.3.6-1, is OPERABLE.
1.
Manual Initiation The LCO requires two channels OPERABLE.
The operator can initiate Containment ventilation isolation at any time by using either of two switches in the control room (containment isolation Phase A switches).
Either switch actuates both trains. This action will cause actuation of all components in the same manner as any of the automatic actuation signals.
The LC0 for Manual Initiation ensures the proper amount of redundancy is maintained in the manual actuation circuitry to ensure the operator has manual initiation capability.
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Each channel consists of one CIA handswitch and the
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interconnecting wiring to the actuation logic cabinet.
(continued)
Vogtle Units 1 and 2 B 3.3-146 Amendment no.105 (unit 1)
Amendment No. 83 (Unit 2) 4
Containment Ventilation Isolation Instrumentation B 3.3.6 '
BASES LCO 2.
Automatic Actuation Loaic and Actuation Relays (continued)
The LCO requires two channels of Automatic Actuation Logic and Actuation Relays OPERABLE to ensure that no single random failure can prevent automatic actuation.
Automatic Actuation Logic and Actuation Relays consist l
of the same features and operate in the same manner as described for ESFAS Function 1.b, SI. The applicable MODES and specified conditions for the Containment ventilation isolation portion of these Functions are different and less restrictive than those for their SI roles.
If one or more of the SI Functions becomes inoperable in such a manner that only the Containment Ventilation Isolation Function is affected, the Conditions applicable to their SI Functions need not be entered. The less restrictive Actions specified for inoperability of the Containment Ventilation Isolation Functions specify sufficient compensatory measures for this case.
3.
Containment Radiation The LCO specifies two required channels of radiation monitors to ensure that the radiation monitoring i
instrumentation necessary to initiate Containment ventilation isolation remains OPERABLE. During CORE ALTERATIONS or movement of irradiated fuel assemblies i
in containment, the required channels provide input to control room alarms to ensure prompt operator action to manually close the containment purge and exhaust valves.
It is also acceptable during CORE ALTERATIONS or movement of irradiated fuel to meet the requirements of this LCO by maintaining the radiation monitoring instrumentation necessary to initiate containment ventilation isolation OPERABLE, in accordance with the requirements stated for MODES 1, 2, 3, and 4 operability. The purge exhaust radiation detectors (RE-2565A, B&C) are treated as one channel which is considered OPERABLE if the particulate (RE-2565A) and iodine (RE-2565B) monitors are OPERABLE or the noble gas monitor (RE-2565C) is OPERABLE.
In addition, two individual channels of containment area low range gamma monitors (RE-0002 &
RE-0003) are provided. The two required radiation monitoring channels may be made up of any combination of the above described channels.
(continued)
Vogtle Units 1 and 2 B 3.3-147
^**d"'eot N.105 (Unit 1)
Amendment No.
8., (Unit 2)
l Containment Ventilation Isolation Instrumentation B 3.3.6 BASES LCO 3.
Containment Radiation (continued)
For sampling systems, channel OPERABILITY involves more than OPERABILITY of the channel electronics.
OPERABILITY may also require correct valve lineups, sample pump operation, and filter motor operation, as well as detector OPERABILITY, if these supporting features are necessary for trip to occur under the conditions assumed by the safety analyses.
(continued)
Vogtle Units 1 and 2 B 3.3-147a Amendment No.105 Unit 1 l
Amendment No. 83 Unit 2
Containment Ventilation Isolation Instrumentation B 3.3.6 BASES-i This Page Intentionally Left Blank l
i l-l (continued)
Vogtle Units 1 and 2 B 3.3-147b Amendment No: 105 (Unit 1 Amendment No. 83 (Unit 2
Containment Ventilation Isolation Instrumentation B 3.3.6 I
BASES LCO 4.
Safety Iniection (continued)
Refer to LCO 3.3.2, Function 1 for all initiating Functions and requirements.
Tbesafetyinjection initiation function is applicable in MODES 1, 2, 3 l
and 4 only.
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APPLICABILITY The Manual Initiation, Automatic Actuation Logic and Actuation Relays, Containment Radiation 'and Safety InjectionFunctionsarerequiredOPERABl.EinMODES1,2,3, and 4.. Under these conditions, the potential exists for an l
accident that could release fission product radioactivity into containment.
Therefore, the Containment ventilation isolation instrumentation must be OPERABLE in these MODES.
During CORE ALTERATIONS or movement of irradiated fuel assemblies in containment, the air locks may be open provided they are isolable per LC0 3.9.4.
Since the air locks can only be closed manually, it is assumed that containment ventilation isolation is accomplished by manually closing the purge and exhaust ventilation valves.
Therefore, only OPERABLE radiation monitors are required to alert the operators of the need for containment ventilation isolation.
While in MODES 5 and 6 without fuel handling in progress,d the containment ventilation isolation instrumentation nee not be OPERABLE since the potential for radioactive releases is minimized and operator action is sufficient to ensure post accident offsite doses are maintained within the limits of Reference 1.
ACTIONS The most common cause of channel inoperability is outright failure or drift of the bistable or process module sufficient to exceed the tolerance allowed by unit specific calibration procedures. Typically the drift is found to be small and results in a delay of actuation rather than a total loss of function.
This determination is generally made during the performance of a COT, when the process instrumentation is set up for adjustment to bring it within specification.
If the Trip Setpoint is less conservative than the tolerance specified by the calibration procedure the channel must be declared inoperable immediately and tbe appropriate Condition entered.
A Note has been added to the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed in Table 3.3.6-1.
The Completion Time (s) of (continued)
Vogtle Units 1 and 2 B 3.3-148 Amendment No. 105 Unit 1 L
Amendment No. 83 Unit 2 1
. ~,.
Containment Ventilation Isolation Instrumentation B 3.3.6
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BASES ACTIONS the inoperable channel (s) of a Function will be tracked (continued separately for each Function starting from the time the Condition was entered for that Function.
M Condition A applies to the failure of one required containment ventilation isolation radiation monitor channel.
The failed channel must be restored to OPERABLE status.
Four hours are allowed to restore the affected channel based i
on the low likelihood of events occurring during this interval, and recognition that one or more of the remaining channels will respond to most events.
u Condition B applies to all Containment Ventilation Isolation Functions and addresses the train orientation of the Solid State Protection System (SSPS) and the master and slave relays for these Functions.
It also addresses the failure of multiple radiation monitoring channels, or the inability to restore a single failed channel to OPERABLE status in the time allowed for Required Action A.I.
If a manual or automatic actuation channel is inoperable, no radiation monitoring channels operable, or the Required Action and associated Completion Time of Condition A are not met, operation may continue as long as the Required Action for the applicable Conditions of LCO 3.6.3 is met for each valve made inoperable by failure of isolation instrumentation.
A Note is added stating that Condition B is only applicable in MODE 1, 2, 3, or 4.
C.1 and C.2 Condition C addresses the failure of multiple radiation I
monitoring channels, or the inability to restore a single failed channel to OPERABLE status in the time allowed for (continued)
Vogtle Units 1 and 2 B 3.3-149 Amendment No. 105 Unit 1 Amendment No. 83 Unit 2
u
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Containment Ventilation Isolation Instrumentation B 3.3.6 BASES ACTIONS' C.1-and C.2 (continued)
Required Action A.I.
If no radiation monitoring channels l
are operable or the Required Action and associated Completion Time of Condition A are not met, operation may continue as long as the Required Action to place and maintain containment purge supply and exhaust isolation valves in their closed position is met or the applicable Conditions of LCO 3.9.4, " Containment Penetrations," are met for each penetration not in the required status. The l
Completion Time for these Required Actions is Immediately.
A Note states that Condition C is applicable during CORE ALTERATIONS and during movement of irradiated fuel assemblies within containment.
SURVEILLANCE A Note has been added to the SR Table to clarify that REQUIREMENTS Table 3.3.6-1 determines which SRs apply to which Containment Ventilation Isolation Functions.
SR 3.3.6.1 Performance of the CHANNEL CHECK once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel to a similar parameter on other channels.
It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value.
Significant deviations between the two instrument channels could be an indication of excessive instrument drift in one of the channels or of something even more serious. A CHANNEL CHECK will detect gross channel failure;_ thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.
Agreement criteria are determined by the unit staff, based on a combination of the channel instrument uncertainties, including indication and readability.
If a channel is (continued)
Vogtle Units 1 and 2 B 3.3-150 Amendment No. 105 Unit 1 Amendment No. 83 Unit 2
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Containment Ventilation Isolation Instrumentation B 3.3.6 BASES SURVEILLANCE SR 3.3.6.4 REQUIREMENTS (continued)
A COT is performed every 92 days on each required channel to ensure the entire channel will perform the intended Function.
The Frequency is based on the staff recommendation for increasing the availability of radiation monitors according to NUREG-1366 (Ref. 2).
For MODES 1, 2, 3, and 4, this test verifies the capability of the instrumentation to provide the containment purge and exhaust system isolation. During CORE ALTERATIONS and movement of irradiated fuel in containment, this test verifies the capability of the required channels to generate the signals required for input to the control room alarm.
The setpoint shall be left consistent with the current unit specific calibration procedure tolerance.
SR 3.3.6.5 SR 3.3.6.5 is the performance of a SLAVE RELAY TEST. The SLAVE RELAY TES1 is the energizing of the slave relays.
Contact operation is verified in one of two ways. Actuation equipment that may be operated in the design mitigation mode is either allowed to function or is placed in a condition where the relay contact operation can be verified without operation of the equipment. Actuation equipment that may not be operated in the design mitigation node is prevented from operation by the SLAVE RELAY TEST circuit.
For this latter case, contact operation is verified by a continuity check of the circuit containing the slave relay. This test is performed every 92 days.
The Frequency is acceptable based on instrument reliability and industry operating experience.
SR 3.3.6.6 SR 3.3.6.6 is the performance of a TADOT. This test is a check of the Manual Actuation Functions and is performed every 18 months.
Each Manual Actuation Function is tested up to, and including, the master relay coils.
In some instances, the test includes actuation of the end device (i.e., pump starts, valve cycles, etc.).
The test also includes trip devices that provide actuation signals directly to the SSPS, bypassing the analog process control equipment.
The SR is modified by a Note that excludes verification of setpoints during the TADOT. The (continued)
Vogtle Units 1 and 2 B 3.3-152 Amendment No.105 (Unit 1)
Amendment No. 83 (Unit 2)
CST 3.7.6 3.7 ' PLANT SYSTEMS 3.7.6 Condensate Storage' Tank (CST).
'One CST shall be OPERABLE with a safety-related volume-a: 340,000 gallons.
-APPLICABILITY:
' MODES 1, 2, and 3, ACTIONS t
-CONDITION REQUIRED ACTION COMPLETION TIME A.
CST volume not within A.1 A1.ign Auxiliary 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limit.
Feedwater pumps to OPERABLE CST.
i.
B.
Required Action and B.1 Be_in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.
eSQ B.2 Be in MODE 4 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIRENENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST volume is within limit.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Vogtle Units 1 and 2 3.7-15 Amendment No.105(Unit 1)
Amendment No. 83(Unit 2)
v CST 3.7.6 Deleted This Page Intentionally Left Blank 1
i 1
.Vogtle Units 1 and2 3.7-16 Amendment No.105(Unit 1)
Amendment No. 83(Unit 2)
t CST B 3.7.6 l
BASES LCO established in Reference 4 and exceeds the volume required (continued) by the accident analysis.
The OPERABILITY of the CST is determined by maintaining the tank level at or above the minimum required level.
Either CST V4001 or CST V4002 may be used to satisfy the LCO requirement.
APPLICABILITY In MODES 1, 2, and 3, the CST is required to be OPERABLE.
Due to the reduced heat removal requirements and short period of time in MODE 4 and the availability of RHR in MODE 4, the LCO does not require a CST to be OPERABLE in this MODE.
In MODE 5 or 6, the CST is not required because the AFW System is not required.
(continued)
Amendment No.105 (Unit 1)
Vogtle Units 1 and 2 B 3.7-37 Amendment No.
83 (Unit 2)
s Containrent Penetrations 3.9.4 a
3.9 REFUELING OPERATIONS 3.9.4 Containment Penetrations LCO 3.9.4 The containment penetrations shall be in the following i
status:
The equipment hatch closed and held in place by four a.
bolts; b.
The emergency and personnel air locks are isolated by at least one air lock door, or if open, the emergency and personnel air locks are isolable by at least one air lock door with a designated individual available to l
close the open air lock door (s); and 1
c.
Each penetration providing direct access from the containment atmosphere to the outside atmosphere either:
1.
closed by a manual or automatic isolation valve, blind flange, or equivalent, or 1
2.
capable of being closed by at least two OPERABLE Containment Ventilation Isolation valves.
4 APPLICABILITY:
During CORE ALTERATIONS, i.
During movement of irradiated fuel assemblies within containment.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more A.1 Suspend CORE Immediately containment ALTERATIONS.
penetrations not in required status.
AND A.2 Suspend movement of Immediately irradiated fuel assemblies within containment.
1 Vogtle Units 1 and 2 3.9-6 Amendment No.105 (Unit 1)
Amendment No. 83 (Unit 2)
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Containment Penetrations 3.9.4 SURVEILLANCE REQ.iR2MENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify each required containment 7 days penetration is in the required status.
NOTE--------------------
Only required for unisolated penetrations.
Verify at least two containment ventilation 18 months valves in each open containment ventilation penetration providing direct access from the containment atmosphere to the outside atmosphere are ca the control room.pable of being closed from 1
Vogtle Units 1 and 2 3.9-7 Amendment No.10XUnit 1)
Amendment No. 8% Unit 2)
c.
4 Containment Penetrations B 3.9.4 BASES BACKGROUND required.
During periods of unit shutdown when containment (continued) closure is not required, the door interlock mechanism may be disabled, allowing both doors of an air lock to remain open for extended periods when frequent containment entry is necessary.
During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, the door interlock mechanism may remain disabled, but one air lock door must always must be isolable by at least one air lock door with a designated individual available to cloca the air lock door, or at least one air lock door must bc
'd.
The requirements for containment penetration closure are sufficient to ensure fission product radioactivity release from containment due to a fuel handling accident during refueling is maintained to within the acceptance criteria of i
Standard Review Plan Section 15.7.4 and General Design Criteria 19.
The Containment Ventilation System consists of two 24 inch 1
penetrations for purge and exhaust of the containment atmosphere.
Each main or shutdown purge and exhaust system contains one motor operated 24 inch valve inside containment and one motor operated 24 inch valve outside containment (HV-2626A, HV-2627A, HV-2628A, and HV-2629A). A second 14 inch mini-purge and exhaust system shares each 24 inch penetration and consists of one 14 inch pneumatically operated valve inside containment and one outside of containment (HV-26268, HV-26278, HV-26288, and HV-26298). A 14 inch mini-purge line is connected to each 24 inch line between the 24 inch isolation valve and the penetration both inside and outside containment.
In MODES 1, 2, 3 and 4 the 24 inch main or shutdown purge and exhaust valves are secured in the closed position. The 14 inch mini-purge and exhaust valves may be opened in these MODES in accordance with LC0 3.6.3, Containment Isolation Valves, and are automatically closed by a Containment Ventilation Isolation signal.
The instrumentation that provides the automatic isolation function for these valves 4
is listed in LCO 3.3.6, Containment Ventilation Isolation Instrumentation.
(continued)
AmendmentNo.105 (Unit 1)
Vogtle Units 1 and 2 B 3.9-14 Amendment No. 83 (Unit 2)
.O i
Containment Penetrations B 3.9.4 BASES BACKGROUND In MODE 6, the 24 inch main or shutdown purge and exhaust (continued) valves are used to exchange large volumes of containment air to support refueling operations or other maintenance activities. During CORE ALTERATIONS or movement of irradiated fuel assemblies within containment any open 24 inch valves are capable of being closed (LCO 3.3.6).
The 14 l
inch mini-purge and exhaust valves, though typically not opened during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment, if opened are also capable of being closed (LCO 3.3.6).
The other containment penetrations that provide direct access from containment atmosphere to outside atmosphere must be isolated on at least one side.
Isolation may be achieved by a closed automatic isolation valve, a manual isolation valve, blind flange, or equivalent.
Equivalent isolation methods allowed under the provisions of 10 CFR 50.59 may include use of a material that can provide a temporary, atmospheric pressure, ventilation barrier for the other containment penetrations during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment (Ref. 1).
APPLICABLE During CORE ALTERATIONS or movement of irradiated fuel SAFETY ANALYSES assemblies within containment, the most severe radiological consequences result from a fuel handling accident.
The fuel handling accident is a postulated event that involves damage to irradiated fuel (Ref. 2).
Fuel handling accidents, analyzed in Reference 3, include dropping a single irradiated fuel assembly onto another irradiated fuel assembly.
To' support the plant configuration of both air lock doors open (personnel and/or emergency air locks), it was l
assumed in FSAR calculations for dose analysis that the designated individual for closure of the air lock would have the air lock closed within 15 minutes of the fuel handling accident. The 15 minute duration was chosen as the limit for the response capability for the person who is designated for closing the air lock door.
The NRC (continued)
Amendment No.105 (Unit 1)
Vogtle Units 1 and 2 B 3.9-15 Amendment tio. 83 (Unit 2)
Containment Penetrations B 3.9.4 BASES APPLICABLE acceptance of this specification was based on doses for a 2 SAFETY ANALYSES hour release as well as a licensee commitment for a person (continued) designated to close the door quickly.
Also, the requirements of LCO 3.9.7, " Refueling Cavity Water Level," and the minimum decay time of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> prior to CORE ALTERATIONS ensure that the release of fission product radioactivity, subsequent to a fuel handling accident, results in doses that are well within the guideline values specified in 10 CFR 100. Standard Review Plan, Section 15.7.4, Rev. 1 (Ref. 3), defines "well within" 10 CFR 100 to be 25% or less of the 10 CFR 100 values. The acceptance limits for offsite radiation exposure will be 25%
of 10 CFR 100 values or the NRC staff approved licensing basis (e.g., a specified fraction of 10 CFR 100 limits).
The radiological consequences of a fuel handling accident in containment have been evaluated assuming that the containment is open to the outside atmosphere. All airborne activity reaching the containment atmosphere is assumed to be exhausted to the environment within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the accident. The calculated offsite and control room operator doses are within the acceptance criteria of Standard Review Plan 15.7.4 and GDC 19. Therefore, although the containment penetrations do not satisfy any of the NRC Policy Statement criteria, LC0 3.9.4 provides containment closure capability to minimize potential offsite doses.
LCO This LCO limits the consequences of a fuel handling accident in containment by limiting'the potential escape paths for fission product radioactivity released within containment.
The LCO requires the equipment hatch and any-penetration providing direct access from the containment atmosphere to the outside atmosphere to be closed.
Personnel air lock closure capability is provided by the availability of at least one door and a designated individual to close it.
Emergency air lock closure capability is provided by the availability of at least one door and a designated individual to close it.
For the OPERABLE containment ventilation penetrations, this LC0 ensures that each penetration is isolable by the Containment Ventilation Isolation valves. The OPERABILITY requirements for LCO 3.3.6, Containment Ventilation Isolation Instrumentation ensure that radiation monitor inputs to the control room alarm exist so that operators can take timely (continued)
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4 Containment Penetrations B 3.9.4 l
BASES LCO action to close containment penetrations to minimize (continued) potential offsite doses. The LC0 requirements for penetration closure may also be met by the automatic isolation capability of the CVI system.
Item b of this LCO includes requirements for both the emergency air lock and the personnel air lock.
The personnel and emergency air locks are required by Item b of this LCO to be isolable by at least one air lock door in each air lock. Both containment personnel and emergency air lock doors may be open during movement of irradiated fuel in the containment and during CORE ALTERATIONS provided at least one air lock door is isolable in each air lock. An air lock is isolable when the following criteria are satisfied:
1.
one air lock door is OPERABLE, l
j 2.
at least 23 feet of water shall be maintained over the top of the reactor vessel flange in accordance with Specification 3.9.7, 3.
a desi door. gnated individual is available to close the OPERABILITY of a containment air lock door requires that the l
door seal arotectors are easily removed, that no cables or hoses are seing run through the air lock, and that the air lock door is capable of being quickly closed.
(continued)
Amendment No.105 (Unit 1)
Vogtle Units 1 and 2 B 3.9-17 Amendment No. 83 (Unit 2) l
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4 Containment Penetrations B 3.9.4 BASES (continued)
APPLICABILITY The containment penetration requirements are applicable i
during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment because this is when there is a potential for a fuel handling accident.
In MODES 1, 2, 3, and 4, containment penetration requirements are addressed by LCO 3.6.1, " Containment." In MODES 5 and 6, when CORE
' ALTERATIONS or movement of irradiated fuel assemblies within containment are not being conducted, the potential for a fuel handling accident does not exist. Therefore, under these conditions no requirements are placed on containment penetration status, i
ACTIONS A.1 and A.2 If the containment equipment hatch, air locks, or any containment penetration that provides direct access from the containment atmosphere to the outside atmosphere is not in the required status, the unit must be placed in a condition where the isolation function is not needed. This is accomplished by immediately suspending CORE ALTERATIONS and movement of irradiated fuel assemblies within containment.
Performance of these actions shall not preclude completion of movement of a component to a safe position.
SURVEILLANCE SR 3.9.4.1 REQUIREMENTS This Surveillance demonstrates that each of the containment penetrations required to be in its closed position is in that position. The Surveillance on the required open containment ventilation isolation valves will demonstrate that the valves are not blocked from closing. Also the Surveillance will demonstrate that each required valve 1
operator has motive power, which will ensure that each valve is capable of being closed.
l The Surveillance is performed every 7 days during CORE ALTERATIONS or movement of irradiated fuel assemblies within containment. The Surveillance interval is selected to be commensurate with the normal duration of time to complete fuel handling operations.
Including a surveillance before the start of refueling operations will provide two or three surveillance verifications during the applicable period for this LCO. As such, this Surveillance ensures that a postulated fuel handling accident that releases fission (continued)
Amendment No.105 (Unit 1)
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Containment Penetrations B 3.9.4 BASES SURVEILLANCE SR 3.9.4.1 (continued)
REQUIREMENTS product radioactivity within the containment will not result in a release of. fission product radioactivity to the environment.
SR 3.9.4.2 This Surveillance demonstrates that each containment ventilation isolation valve in each open containment ventilation penetration actuates to its isolation position.
The 18 month Frequency maintains consistency with other similar testing requirements. Also, SR 3.6.3.5 demonstrates that the isolation time of each valve is in accordance with the Inservice Testing Program requirements. These Surveillances Performed during MODE 6 will ensure that the valves are capable of closing after a postulated fuel handling accident to limit a release of fission product radioactivity from the containment.
REFERENCES 1.
GPU Nuclear Safety Evaluation SE-0002000-001, Rev. 0, May 20, 1988.
2.
FSAR, Subsection 15.7.4.
3.
NUREG-0800, Section 15.7.4, Rev. 1, July 1981.
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Vogtle Units 1 and 2 B 3.9-19 Amendment No.105 (Unit 1)
Amendment No. 83 (Unit 2)
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