LR-N04-0238, Request for Change to Technical Specifications, to Modify Definition of Operable
| ML042160223 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/23/2004 |
| From: | Brothers M Public Service Enterprise Group |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| LCR S04-06, LR-N04-0238 | |
| Download: ML042160223 (23) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 JUL 2 3 2004 0 PSEG NuclearLLC LR-N04-0238 LCR S04-06 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS DEFINITION OF OPERABLE SALEM GENERATING STATION UNIT NOS. I AND 2 DOCKET NOS. 50-272 AND 50-311 FACILITY OPERATING LICENSE NO. DPR-70 AND DPR-75 Pursuant to 10 CFR 50.90, PSEG Nuclear LLC (PSEG) hereby requests approval of a change to the Technical Specifications for Salem Generating Station Units 1 and 2. In accordance with 10CFR50.91(b)(1), a copy of this submittal has been sent to the State of New Jersey.
The proposed changes contained herein modify the definition of OPERABLE to conform to the Improved Technical Specifications (NUREG-1431, Rev. 3, "Standard Technical Specifications for Westinghouse Plants.") and incorporate appropriate conditions into electrical power systems TS 3.8.1.2, Electrical Power Systems - Shutdown. In addition, TS 3.8.2 for Electrical Distribution - Shutdown are modified.
PSEG has evaluated the proposed changes in accordance with 10CFR50.91(a)(1),
using the criteria in 10CFR50.92(c), and has determined this request involves no significant hazards considerations. An evaluation of the requested changes is provided in Attachment I to this letter. The marked up Technical Specification pages affected by the proposed changes are provided in Attachment 2.
Approval of this request is needed to support Salem 2 Refueling Outage 2R14.
Therefore, PSEG requests approval of the proposed License Amendment by January 31, 2005 to be implemented within 60 days.
95-2168 REV. 7/99
Document Control Desk Document Control Desk LR-N04-0238 I declare under penalty of perjury that the foregoing is true and correct.
Executed on 7 (DaZt/Z
'(Date)
Sincerely, Michael H. Brother Vice President - Site 0 ~rations Attachments (2)
Document Control Desk LR-N04-0238 C:
Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Collins, Project Manager - Salem & Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08C2 Washington, DC 20555 USNRC Senior Resident Inspector-Salem (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 08625
Document Control Desk LR-N04-0238 Attachment I LCR S04-06 SALEM GENERATING STATION UNITS 1 AND 2 FACILITY OPERATING LICENSES NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 EVALUATION OF CHANGES TO THE TECHNICAL SPECIFICATIONS REGARDING THE DEFINITION OF OPERABLE Table of Contents
- 1.
DESCRIPTION...........................................................
1
- 2.
PROPOSED CHANGE...........................................................
1
- 3.
BACKGROUND...........................................................
1
- 4.
TECHNICAL ANALYSIS...........................................................
2
- 5.
REGULATORY SAFETY ANALYSIS.........................................................
3 5.1 No Significant Hazards Consideration........................................................ 3 5.2 Applicable Regulatory Requirements/Criteria............................................. 4
- 6.
ENVIRONMENTAL CONSIDERATION.........................................................
5
- 7.
REFERENCES..................................................................................................... 5
Document Control Desk LR-N04-0238 Attachment I LCR S04-06 REQUEST FOR CHANGE TO THE UFSAR
- 1.
DESCRIPTION The purpose of this change is to modify the definition of OPERABLE to conform to the Improved Technical Specifications (NUREG-1431, Rev. 3, "Standard Technical Specifications for Westinghouse Plants.") and incorporate appropriate conditions into electrical power systems limiting Conditions for Operation (LCOs) for AC & DC Sources and Distribution during Modes 5 & 6 and during movement of irradiated fuel assemblies.
- 2.
PROPOSED CHANGE PSEG is requesting that the definition of OPERABLE be changed to conform to the definition in Improved Technical Specifications (ITS) allowing equipment to be considered OPERABLE with either normal or emergency electrical power available. Changes to the Technical Specifications (TS) for electrical power systems for AC & DC Sources and Distribution during Modes 5 & 6 and during movement of irradiated fuel assemblies are also revised to conform to ITS.
These changes extend the relief granted by Amendments 253/234 to the shutdown modes and allow declaring supported systems inoperable rather than always suspending core alterations.
The above changes are shown on the attached proposed changed pages (Attachment 2). Changes to be inserted in the bases for Electrical Power Systems are also included in attachment 2.
- 3.
BACKGROUND On November 1, 2001, PSEG Nuclear LLC submitted License Change Request (LCR) S01-02 (LR-N01-0200) to incorporate ITS provisions regarding operability of normal and emergency power during Modes 1 - 4. LCR S01-02 was supplemented by letter dated October 1, 2002 (LR-N02-0332). LCR S01 -02 was approved by License Amendments 253 and 234 for Unit 1 and Unit 2, respectively. The above amendments did not change the definition of OPERABLE and did not address modes 5 and 6. The changes proposed by this request extend flexibility to cover Modes 5 & 6 and revise the definition of OPERABLE to coordinate with the LCOs of TS section 3/4 3.8. The proposed changes are intended to provide outage scheduling flexibility and avoid unnecessary disruption of refueling activities while still providing for appropriate actions to assure nuclear safety.
1
Document Control Desk LR-N04-0238 Attachment I LCR S04-06
- 4.
TECHNICAL ANALYSIS The proposed change's improve clarity of the TS and remove potential conflicting requirements. The current TS can be interpreted to require equipment supported by an inoperable AC source to also be declared inoperable, since the definition of OPERABLE in the Salem Unit 1 & 2 TS specifies that both "normal and emergency power" are needed. However, TS 3.8.1.1 allows operation to continue up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for an A.C. circuit, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for 2 inoperable A.C. circuits, or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for a diesel generator before equipment supported by an inoperable AC source needs to be declared inoperable, if the redundant supported equipment is inoperable. Specification 3.8.1.1 is intended to allow operation to be governed by the time limits of the action statement associated with the Limiting Condition for Operation (LCO) of the normal or emergency power source, rather than the corresponding action statement for each affected system or component. The proposed changes to the definition of OPERABLE are consistent with ITS and specifies that either "normal or emergency power" are needed. The proposed change to the definition of OPERABLE removes any potential confusion.
The LCOs for AC & DC Sources and Distribution during Modes 5 & 6 and during movement of irradiated fuel assemblies are also modified to be consistent with the intent of ITS. (Note: The ITS LCO for distribution while shutdown is 3.8.10 while equivalent Salem LCOs are 3.8.2.2, 3.8.2.4, and 3.8.2.6. Also ITS LCO 3.8.5 for D.C. sources shutdown is covered by Salem LCOs 3.8.2.4 and 3.8.2.6.
In addition, ITS LCO 3.8.8 for Inverters shutdown is covered by Salem LCO 3.8.2.2.) The current TS requires suspending core alterations when any A.C. or D.C. source is lost in Modes 5 & 6 or during movement of irradiated fuel. The proposed changes provide an option to take action in accordance with the LCO for the affected required features when a required power source (A.C. or D.C.) or distribution system (A.C. or D.C.) is lost or to take action to suspend all operations involving CORE ALTERATIONS or positive reactivity changes until the minimum required power sources or distribution system are restored to OPERABLE status. This flexibility is reasonable since not all power source or distribution system inoperabilities affect equipment required for CORE ALTERATIONS or positive reactivity changes. The LCOs for the affected required features contain requirements to address the condition and to discontinue CORE ALTERATIONS or positive reactivity changes when it is appropriate. Therefore, the proposed changes continue to assure that the plant is placed in a safe condition but avoid overly restrictive actions.
In general, when the unit is shut down, the Technical Specifications requirements ensure that the unit has the capability to mitigate the consequences of postulated accidents. However, assuming a single failure and concurrent loss of all offsite or all onsite power is not required. This allowance allows performance of a significant number of required testing and maintenance activities to be conducted provided an acceptable level of risk is not exceeded.
2
Document Control Desk LR-N04-0238 Attachment I LCR S04-06 Relaxations from MODE 1, 2, 3, and 4 LCO requirements during shutdown modes are justified because, activities are planned and administratively controlled, outage time is limited, and the risk associated with multiple activities that could affect multiple systems is controlled.
The TS ensure that all required loads are powered from offsite power with EDG backup ensures a diverse power source is available to provide electrical power support, assuming a loss of the offsite circuit. Together, OPERABILITY of the required offsite circuit and EDG ensures the availability of sufficient AC sources to operate the unit in a safe manner and to mitigate the consequences of postulated events during shutdown.
- 5.
REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration PSEG Nuclear LLC (PSEG) has evaluated whether or not a significant hazards consideration is involved with the proposed changes by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment" as discussed below:
- 1.
Does the proposed change involve'a significant increase in the probability or consequences of an accident previously evaluated?
Response
No.
The likelihood of an event is not increased since the proposed changes do not alter the number or types of equipment required to be OPERABLE.
Also, the probability of occurrence or the consequences for an accident is not increased by the proposed changes since the minimum configuration of equipment required by individual TS will remain available. Further, the proposed changes do not alter the way any structure, system or component (SSC) functions, do not modify the manner in which the plant is operated, and do not significantly alter equipment out-of-service time.
No changes to the design of structures, systems, or components (SSC) are made and there are no effects on accident mitigation.
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2.
Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response
No.
3
Document Control Desk LR-N04-0238 LCR S04-06 The possibility of a new or different kind of accident from any accident or malfunction in the Salem Updated Final Safety Analysis Report (UFSAR) is not created. The allowable outage time is consistent with requirements of Improved Standard Technical Specifications and does not introduce any new or different failure from any previously evaluated or change the manner in which safety systems are operated. The associated system and equipment configurations are no different from those previously evaluated. Therefore a different accident is not created. In addition, the proposed changes cannot initiate an accident. Further, the proposed changes do not change the design function or operation of any SSCs.
Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3.
Does the proposed change involve a significant reduction in a margin of safety?
Response
No.
The proposed changes continue to provide assurance that an event coincident with failure of an associated diesel generator or offsite power circuit will not result in complete loss of safety function of critical required redundant systems or equipment. In addition, the proposed changes do not change the margin of safety since no SSCs are changed. The results of accident analysis remain unchanged by the proposed.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety.
Based on the above, PSEG concludes that the proposed changes present no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatory Requirements/Criteria General Design Criterion (GDC) 17 of Appendix A to 10 CFR 50 "Electric power systems" applies to this change. The objectives of GDC 17 to provide reliable and diverse electrical power to address plant events continue to be met with the proposed changes. There are no changes to the design of the plant, therefore, the method of compliance with GDC 17 remains unchanged. In addition, the TS ensure that all required loads are powered from offsite power with EDG backup to ensure a diverse power source is available to provide electrical power support, assuming a loss of the offsite circuit. Together, OPERABILITY of the required offsite circuit and EDG ensures the availability of sufficient AC sources to operate 4
Document Control Desk LR-N04-0238 Attachment I LCR S04-06 the unit in a safe manner and to mitigate the consequences of postulated events during shutdown.
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
- 6.
ENVIRONMENTAL CONSIDERATION PSEG has determined the proposed amendment relates to changes in a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or relates to changes in an inspection or a surveillance requirement. The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), an environmental assessment of the proposed change is not required.
- 7.
REFERENCES
- 1. PSEG Letter LR-NO1 -0200, License Change Request LCR S01-02, dated November 1, 2001, "REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS 3.0.5 and 3.8.1 - NORMAL AND EMERGENCY POWER".
- 2. Letter LR-N02-0332, "ADDITIONAL INFORMATION FOR LICENSE CHANGE REQUEST S01-02 REGARDING NORMAL AND EMERGENCY POWER", dated October 1, 2002.
- 3. NRC letter "Salem Nuclear Generating Station, Unit Nos. 1 And 2, Issuance of Amendment Re: Change To Technical Specifications -
Normal And Emergency Power (TAC NOS. MB3453 and MB3454)", dated October 11, 2002.
5
Document Control Desk LR-N04-0238 LCR S04-06 SALEM NUCLEAR GENERATING STATION UNITS I & 2 FACILITY OPERATING LICENSES NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 CHANGES TO THE TECHNICAL SPECIFICATIONS (TS)
TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specification pages for Facility Operating Licenses DPR-70 (Unit 1) and DPR-75 (Unit 2) are affected by this change request:
TS Section Unit 1 Paae 1.18 1-4 3.8.1.2 3/4 8-5c Unit 2 Page 1-4 3/4 8-7a 3/4 8-9 3/4 8-12 3/4 8-15 3.8.2.2 3/4 8-7 3.8.2.4 3/4 8-10 3.8.2.6 3/4 8-13 Insert for Bases 3/4.8 B 3/4 8-2 B 3/4 8-2 I
DEFINITIONS
- b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or
- c.
Reactor coolant system leakage through a steam generator to the secondary system.
MEMBER(S) OF THE PUBLIC 1.16 MEMBER(S) OF THE PUBLIC shall be all those persons who are not occupationally associated with the plant.
This category does not include employees of PSE&G, its contractors, or vendors.
Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
OFESITE DOSE CALCULATION MANUAL (ODCM) 1.17 The OFFSITE 'DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.
The ODCM shall also contain (1) the Radioactive Effluent controls and Radiological Environmental Monitoring programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.7 and 6.9.1.8 respectively.
OPERABLE -
OPERABILITY 1.18 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
OPERATIONAL MODE -
MODE 1.19 An OPERATIONAL MODE (ie., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
SALEM -
UNIT 1 1-4 Amendment No.
DEFINITIONS
- b.
Leakage into the containment atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE, or
- c.
Reactor coolant system leakage through a steam generator to the secondary system.
MEMBER(S) OF THE PUBLIC 1.16 MEMBER(S) OF THE PUBLIC shall be all those persons who are not occupationally associated with the plant.
This category does not include employees of PSE&G, its contractors, or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
This category does include persons who use portions of the site for recreational, occupational, or other purposes not associated with the plant.
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.17 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm/Trip setpoints, and in the conduct of the Environmental Radiological Monitoring Program.
The ODCM shall also contain (1) the Radioactive Effluent controls and Radiological Environmental Monitoring programs required by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.7 and 6.9.1.8 respectively.
OPERABLE -
OPERABILITY 1.18 A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
OPERATIONAL MODE -
MODE 1.19 An OPERATIONAL MODE (ie., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level and average reactor coolant temperature specified in Table 1.1.
SALEM -
UNIT 2 1-4 Amendment No.
ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a.
One circuit between the offsite transmission network and the onsite Class lE distribution system (vital bus system), and
- b.
Two separate and independent diesel generators with:
- 1.
Separate day tanks containing a minimum volume of 130 gallons of fuel, and
- 2.
A common fuel storage system containing a minimum volume of 23,000 gallons of fuel, and
- 3.
A fuel transfer pump.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE, (immediately declare the affected required features inoperable, orC suspend all operations involving CORE ALTERATIONS or positive reactivity changes until the minimum required A.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS
NOTE ----------------------------------
-NTE The following surveillances are not required to be performed to maintain operability during Modes 5 and 6.
These surveillances are: 4.8.1.1.1.b, 4.8.1.1.2.d.2, 4.8.1.1.2.d.3, 4.8.1.1.2.d.4, 4.8.1.1.2.d.6, 4.8.1.1.2.d.9, 4.8.1.1.2.e, 4.8.1.1.2.f, and 4.8.1.1.2.g.
4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1, 4.8.1.1.2, 4.8.1.1.3 (except for requirement 4.8.1.1.3.a.2) and 4.8.1.1.4.
SALEM -
UNIT 1 3/4 8-5c Amendment No.
ELECTRICAL POWER SYSTEMS A.C. DISTRIBUTION -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, two A.C. electrical bus trains shall be OPERABLE and energized from sources of power other than a diesel generator but aligned to an OPERABLE diesel generator with each train consisting of:
1 -
4 kvolt Vital Bus 1 -
460 volt Vital Bus and associated control centers 1 -
230 volt Vital Bus and associated control centers 1 -
115 volt Instrument Bus energized from its respective inverter connected to its respective D. C. bus train.
APPLICABILITY: MODES 5 and 6.
During movement of irradiated fuel assemblies.
ACTION:
With less than the above complement of A.C. busses and inverters OPERABLE and energized, e
suspend all operations involving CORE ALTERATIONS, positive reactivity changes, and movement of irradiated fuel assemblies until the minimum required A.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.8.2.2 The specified A.C. busses shall be determined OPERABLE and energized from A.C. sources other than the diesel generators at least once per 7 days by verifying correct breaker alignment and indicated power availability.
SALEM -
UNIT 1 3/4 8-7 Amendment No.
ELECTRICAL POWER SYSTEMS SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
- a.
One circuit between the offsite transmission network and the onsite Class IE distribution system (vital bus system), and
- b.
Two separate and independent diesel generators with:
- 1.
Separate day tanks containing a minimum volume of 130 gallons of fuel, and
- 2.
A common fuel storage system containing a minimum volume of 23,000 gallons of fuel, and
- 3.
A fuel transfer pump.
APPLICABILITY:
MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE, (immediately declare the affected required features inoperable, or I
suspend all operations involving CORE ALTERATIONS or positive reactivity changes until the minimum required A.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS
__-----------------------NOTE ----------------------------------
-NTE The following surveillances are not required to be performed to maintain operability during Modes 5 and 6. These surveillances are: 4.8.1.1.1.b, 4.8.1.1.2.d.2, 4.8.1.1.2.d.3, 4.8.1.1.2.d.4, 4.8.1.1.2.d.6, 4.8.1.1.2.d.9, 4.8.1.1.2.e, 4.8.1.1.2.f, and 4.8.1.1.2.g.
4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE by the performance of each of the Surveillance Requirements of 4.8.1.1.1, 4.8.1.1.2, 4.8.1.1.3 (except for requirement 4.8.1.1.3.a.2) and 4.8.1.1.4.
SALEM -
UNIT 2 3/4 8-7a Amendment No.
ELECTRICAL POWER SYSTEMS A.C. DISTRIBUTION -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, two A.C. electrical bus trains shall be OPERABLE and energized from sources of power other than a diesel generator but aligned to an OPERABLE diesel generator with each train consisting of:
1 -
4 kvolt Vital Bus 1 -
460 volt Vital Bus and associated control centers 1 -
230 volt Vital Bus and associated control centers 1 -
115 volt Instrument Bus energized from its respective inverter connected to its respective D. C. bus train.
APPLICABILITY: MODES 5 and 6.
During movement of irradiated fuel assemblies.
ACTION:
With less than the above complement of A.C. busses and inverters OPERABLE and energized, g
suspend all operations involving CORE ALTERATIONS, positive reactivity changes, and movement of irradiated fuel assemblies until the minimum required A.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.8.2.2 The specified A.C. busses shall be determined OPERABLE and energized from A.C. sources other than the diesel generators at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses.
SALEM -
UNIT 2 3/4 8-9 Amendment No.
ELECTRICAL POWER SYSTEMS 125-VOLT D.C. DISTRIBUTION -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:
2 -
125-volt D.C. busses, and 2 -
125-volt batteries, each with at least one full capacity charger, associated with each of the above D.C. busses.
APPLICABILITY: MODES 5 and 6.
During movement of irradiated fuel assemblies.
ACTION:
With less than the above complement of D.C. equipment and busses OPERABLE, Simmediately declare the affected required features inoperable, o suspend all operations involving CORE ALTERATIONS, positive reactivity changes, and movement of irradiated fuel assemblies until the minimum required 125Volt D.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.8.2.4.1 The above required 125-volt D.C. busses shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2 The above required 125-volt batteries and chargers shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
SALEM -
UNIT 1 3/4 8-10 Amendment No.
ELECTRICAL POWER SYSTEMS 125-VOLT D.C. DISTRIBUTION -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.4 As a minimum, the following D.C. electrical equipment and bus shall be energized and OPERABLE:
2 -
125-volt D.C. busses, and 2 -
125-volt batteries, each with at least one full capacity charger, associated with each of the above D.C. busses.
APPLICABILITY: MODES 5 and 6.
During movement of irradiated fuel assemblies.
ACTION:
With less than the above complement of D.C. equipment and busses OPERABLE, immediately declare the affected required features inoperable, o suspend all operations involving CORE ALTERATIONS, positive reactivity changes, and movement of irradiated fuel assemblies until the minimum required 125Volt D.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.8.2.4.1 The above required 125-volt D.C. busses shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.
4.8.2.4.2 The above required 125-volt batteries and chargers shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.3.2.
SALEM -
UNIT 2 3/4 8-12 Amendment No
ELECTRICAL POWER SYSTEMS 28-VOLT D.C. DISTRIBUTION -
SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.2.6 As a minimum, the following D. C. electrical equipment and bus shall be energized and OPERABLE:
1 -
28-volt D.C. bus, and 1 -
28-volt battery and at least one full capacity charger associated with the above D.C. bus.
APPLICABILITY:
MODES 5 and 6.
During movement of irradiated fuel assemblies.
ACTION:
With less than the above complement of D.C. equipment and busses OPERABLE, (immediately declare the affected required features inoperable, or suspend all operations involving CORE ALTERATIONS, positive reactivity changes, and movement or irradiated fuel assemblies until the minimum required 28Volt D.C.
electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.8.2.6.1 The above required 28-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and power availability.
4.8.2.6.2 The above required 28-volt batteries and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.5.2.
SALEM -
UNIT 8
3/4 8-13 Amendment No.
ELECTRICAL POWER SYSTEMS 28-VOLT D.C. DISTRIBUTION -
SHUTDOWN LIMITING CONDITION FOR OPERATION
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3.8.2.6 As a minimum, the following D. C.
be energized and OPERABLE:
1 -
28-volt D.C. bus, and electrical equipment and bus shall 1 -
28-volt battery and at least one with the above D.C. bus.
full capacity charger associated APPLICABILITY:
MODES 5 and 6.
During movement of irradiated fuel assemblies.
ACTION:
With less than the above complement of D.C. equipment and busses OPERABLE, immediately declare the affected required features inoperable, o suspend all operations involving CORE ALTERATIONS, positive reactivity changes, and movement or irradiated fuel assemblies until the minimum required 28Volt D.C.
electrical power sources are restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.8.2.6.1 The above required 28-volt D.C. bus shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and power availability.
4.8.2.6.2 The above required 28-volt batteries and charger shall be demonstrated OPERABLE per Surveillance Requirement 4.8.2.5.2.
SALEM -
UNIT 2 3/4 8-15 Amendment No.
Insert for Bases 3/4.8 ELECTRICAL POWER SYSTEMS page 3/4 8-2 An offsite circuit would be considered inoperable if it were not available to one required train. Although two trains are required by LCOs are 3.8.2.2, 3.8.2.4, and 3.8.2.6, the one train with offsite power available may be capable of supporting sufficient required features to allow continuation of CORE ALTERATIONS and irradiated fuel movement. By the allowance of the option to declare required features inoperable, with no offsite power available, appropriate restrictions will be implemented in accordance with the affected required features LCO's actions.
With the offsite circuit not available to all required trains, the option exists to declare all required features inoperable.
Since this option may involve undesired administrative efforts, the allowance for sufficiently conservative actions is made.
With a DG inoperable, the minimum required diversity of AC power sources may not be available.
Therefore, it may be required to suspend CORE ALTERATIONS, movement of irradiated fuel assemblies, and operations involving positive reactivity additions that could result in loss of required shutdown margin or boron concentration.
Suspending positive reactivity additions that could result in failure to meet the minimum shutdown margin or boron concentration limit is required to assure continued safe operation.
3/4.8 ELECTRICAL POWER SYSTEMS BASES (Continued) or components that are associated with the other train that has power, results in starting the completion times for the Action. The specified time is acceptable because it minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown.
The remaining OPERABLE AC supplies (one offsite circuit and three DGs for Condition (a), two offsite circuits and two DGs for Condition (b), or three DGs for Condition (d)) are adequate to supply electrical power to the onsite Class lE Distribution System. Thus, on a component basis, single failure protection for the required system or component's function may have been lost; however, function has not been lost. The completion time takes into account the component OPERABILITY of the redundant counterpart to the inoperable required system or component. Additionally, the completion time takes into account the capacity and capability of the remaining AC sources, a reasonable time for repairs, and the low probability of a DBA occurring during this period. The completion time for Condition d (loss of both offsite circuits) is reduced to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from that allowed for one train without offsite power (Action 3.8.1.1.a.2). The rationale is that Regulatory Guide 1.93 allows a completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for two required offsite circuits inoperable, based upon the assumption that two complete safety trains are OPERABLE. When a concurrent redundant required system or component failure exists, this assumption is not the case, and a shorter completion time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is appropriate.
The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that
- 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.
The Applicability of specifications 3.8.2.2, 3.8.2.4, and 3.8.2.6 includes the movement of irradiated fuel assemblies.
This will insure adequate electrical power is available for proper operation of the fuel handling building ventilation system du movement of irradiated fuel in the spent fuel pool.
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are based upon the recommendations of Regulatory Guide 1.9, "Selection of Diesel Generator Set Capacity for Standby Power Supplies,"
March 10, 1971, and Regulatory Guide 1.108, "Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977. Regulatory Guide 1.108 criteria for determining and reporting valid tests and failures, and accelerated diesel generator testing, have been superseded by implementation of the Maintenance Rule for the diesel generators per 10CFR50.65.
In addition to the Surveillance Requirements of 4.8.1.1.2, diesel preventative maintenance is performed in accordance with procedures based on manufacturer's recommendations with consideration given to operating experience.
The minimum voltage and frequency stated in the Surveillance Requirements (SR) are those necessary to ensure the Emergency Diesel Generator (EDG) can accept Design Basis Accident (DBA) loading while maintaining acceptable voltage and frequency levels.
Stable operation at the nominal voltage and frequency values is also essential in establishing EDG OPERATILITY, but a time constraint is not imposed.
The lack of a time constraint is based on the fact that a typical EDG will experience a period of voltage and frequency oscillations prior to reaching steady state operation if these oscillations are not dampened out by load application. In lieu of a time constraint in SALEM -
UNIT 2 B 3/4 8-2 Amnendment No.234
3/4.8 ELECTRICAL POWER SYSTEMS BASES (Continued)
If at any time during these conditions a redundant required system or component subsequently becomes inoperable, this completion time begins to be tracked.
Discovering no offsite power to one train of the onsite Class lE Electrical Power Distribution System, or one required DG inoperable, coincident with one or more inoperable required support or supported systems or components that are associated with the other train that has power, results in starting the completion times for the Action. The specified time is acceptable because it minimizes risk while allowing time for restoration before subjecting the unit to transients associated with shutdown.
The remaining OPERABLE AC supplies (one offsite circuit and three DGs for Condition (a), two offsite circuits and two DGs for Condition (b), or three DGs for Condition (d)) are adequate to supply electrical power to the onsite Class 1E Distribution System. Thus, on a component basis, single failure protection for the required system or component's function may have been lost; however, function has not been lost. The completion time takes into account the component OPERABILITY of the redundant counterpart to the inoperable required system or component. Additionally, the completion time takes into account the capacity and capability of the remaining AC sources, a reasonable time for repairs, and the low probability of a DBA occurring during this period. The completion time for Condition d (loss of both offsite circuits) is reduced to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from that allowed for one train without offsite power (Action 3.8.1.1.a.2). The rationale is that Regulatory Guide 1.93 allows a completion time of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for two required offsite circuits inoperable, based upon the assumption that two complete safety trains are OPERABLE. When a concurrent redundant required system or component failure exists, this assumption is not the case, and a shorter completion time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is appropriate.
The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that 1) the facility can be maintained in the shutdown or refueling condition for extended time periods and 2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.
The Applicability of specifications 3.8.2.2, 3.8.2.4, and 3.8.2.6 includes the movement of irradiated fuel assemblies.
This will insure adequate electrical power is available for proper operation of the fuel handling building ventilation system during movement of irradiated fuel in the spent fuel pool.
The Surveillance Requireme trating the OPERABILITY of the diesel generators are based upon the recommendations of Regulatory Guide 1.9, "Selection of Diesel Generator Set Capacity for Standby Power Supplies,"
March 10, 1971, and Regulatory Guide 1.108, "Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977. Regulatory Guide 1.108 criteria for determining and reporting valid tests and failures, and accelerated diesel generator testing, have been superseded by implementation of the Maintenance Rule for the diesel generators per 10CFR50.65.
In addition to the Surveillance Requirements of 4.8.1.1.2, diesel preventative maintenance is performed in accordance with procedures based on manufacturer's recommendations with consideration given to operating experience.
SALEM - UNIT I B 3/4 8-2 Amendment No. 253