ML032810110
| ML032810110 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| Issue date: | 09/26/2003 |
| From: | Oatley D Pacific Gas & Electric Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| DCL-03-118 | |
| Download: ML032810110 (75) | |
Text
51 Pacific Gas and
/
fElectric Company David H. Outley Diablo Canyon Power Plant Vice President and PO. Box 56 General Manager Avila Beach, CA 93424 September 26, 2003 805.545.4350 Fax: 805.545.4234 PG&E Letter DCL-03-118 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 License Amendment Request 03-13 Anplication for Technical Specification Chanae Regarding Mode Chanae Limitations Using the Consolidated Line Item Improvement Process
Dear Commissioners and Staff:
In accordance with the provisions of 10 CFR 50.90, Pacific Gas and Electric Company (PG&E) is submitting a request for an amendment to the Technical Specifications (TS) for Facility Operating License Nos. DPR-80 and DPR-82 for Units 1 and 2 of the Diablo Canyon Power Plant (DCPP), respectively.
The proposed amendment would modify TS requirements for mode change limitations in Limiting Condition for Operation 3.0.4 and Surveillance Requirement 3.0.4. This license amendment request (LAR) is consistent with NRC-approved Industry/Technical Specification Task Force (TSTF) Traveler number TSTF-359, 'Increased Flexibility in Mode Restraints." Enclosure 1 contains a description of the proposed change, the supporting technical analyses, and the no significant hazards consideration determination. -Enclosures 2 and 3 contain marked-up and retyped TS pages, respectively. Enclosure 4 provides the marked-up TS Bases changes for information only. TS Bases changes will be implemented pursuant to TS 5.5.14, "Technical Specifications Bases Control Program.'
PG&E has determined that this LAR does not involve a significant hazard consideration as determined per 10 CFR 50.92. Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the issuance of this amendment.
The change in this LAR is not required to address an immediate safety concern.
PG&E requests approval of this LAR no later than October 2004. PG&E requests the LAR be made effective upon NRC issuance, to be implemented within 90 days from the date of issuance.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- South Texas Project
- Wolf Creek 1)01
Document Control Desk PG&E Letter DCL-03-118 September 26, 2003 Page 2 This communication contains no new or revised commitments.
If you have any questions or require additional information, please contact Stan Ketelsen at (805) 545-4720.
Sincerely, David H. Oatley Vice President and General Manager - Diablo Canyon smg/4692 Enclosures cc:
Edgar Bailey, DHS Bruce S. Mallett David L. ProuIx Diablo Distribution cc/enc:
Girija S. Shukla A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- ComanchePeak
- DiabloCanyon
- PaloVerde
- SouthTexasProject
- WolfCreek
PG&E Letter DCL-03-118 UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION
)
Docket No. 50-275 In the Matter of
)
Facility Operating License PACIFIC GAS AND ELECTRIC COMPANY)
No. DPR-80
)
Diablo Canyon Power Plant
)
Docket No. 50-323 Units 1 and 2
)
Facility Operating License
)
No. DPR-82 AFFIDAVIT David H. Oatley, of lawful age, first being duly sworn upon oath says that he is Vice President and General Manager - Diablo Canyon of Pacific Gas and Electric Company; that he has executed License Amendment Request 03-13 on behalf of said company with full power and authority to do so; that he is familiar with the content thereof; and that the facts stated therein are true and correct to the best of his knowledge, information, and belief.
David H. Oatley Vice President and General Manager - Diablo Canyon Subscribed and sworn to before me this 26e day of September, 2003.
Notary Public
/
/
N c
c County of San Lis Obiw Commissin # 1397647 State of California Son Luls Oblspo County j
MyComm. Expims Feb 1,207
Enclosure I PG&E Letter DCL-03-118 EVALUATION
1.0 DESCRIPTION
The proposed amendment would modify Technical Specification (TS) requirements for mode change limitations in Limiting Condition for Operation (LCO) 3.0.4 and Surveillance Requirement (SR) 3.0.4.
The changes are consistent with Nuclear Regulatory Commission (NRC) approved Industry/Technical Specification Task Force (TSTF) Standard TS (STS) change TSTF-359 Revision 8, as modified by the notice in the Federal Register published on April 4, 2003. That Federal Register Notice (FRN) announced the availability of this TS improvement through the Consolidated Line Item Improvement Process (CLIIP). TSTF-359, Revision 8, was subsequently revised to incorporate the modifications discussed in the April 4, 2003, FRN and other minor changes, and was submitted to the NRC on April 28, 2003, as TSTF-359, Revision 9.
2.0 ASSESSMENT
2.1 Applicability of Published Safety Evaluation Pacific Gas and Electric Company (PG&E) has reviewed the safety evaluation dated April 4, 2003, as part of the CLIIP. This review included a review of the NRC staffs evaluation, as well as the information provided to support TSTF-359 Revision 8, and included the updates made in TSTF-359, Revision 9. PG&E has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to Diablo Canyon Power Plant (DCPP) Units I and 2, and justify the incorporation of the changes in the DCPP TS.
2.2 Optional Changes and Variations PG&E is not proposing any variations or deviations from the TS changes described in TSTF-359 Revision 9 and the NRC staffs model safety evaluation dated April 4, 2003.
Due to differences between DCPP TS and TS Bases and the model STS in NUREG-1431, Revision 2, "Standard Technical Specifications, Westinghouse Plants," in several cases variances from the TSTF mark-up changes are made.
These variances are discussed below and do not affect the adoption or application of TSTF-359, Revision 9.
In TS 3.1.1, "Shutdown Margin (SDM)," the Applicability Note stating, 'While this LCO is not met, entry into MODE 5 from MODE 6 is not permitted," is I
Enclosure I PG&E Letter DCL-03-118 deleted. Prior to approval of TSTF-359, LCO 3.0.4 and SR 3.0.4 contained a Reviewer's Note which required a plant-specific evaluation and, if necessary, application of specific restrictions on mode changes or Required Actions in individual LCOs. This plant-specific restriction added as a result of the evaluation described in the Reviewer's Note to LCO 3.0.4 is therefore deleted.
In TS 3.3.1, "Reactor Trip System (RTS) Instrumentation," the Note in Condition C stating, "While this LCO is not met for Function 19, 20 or 21 in MODE 5, making the Rod Control System capable of rod withdrawal is not permitted," is deleted. Prior to approval of TSTF-359, LCO 3.0.4 and SR 3.0.4 contained a Reviewer's Note which required a plant-specific evaluation and, if necessary, application of specific restrictions on mode changes or Required Actions in individual LCOs. This plant-specific restriction added as a result of the evaluation described in the Reviewer's Note to LCO 3.0.4 is therefore deleted.
In TS 3.4.8, 'RCS Loops - MODE 5, Loops Not Filled," the Applicability Note stating, "While the LCO is not met, entry into MODE 5, Loops Not Filled, from MODE 5, Loops Filled, is not permitted," is deleted. Prior to approval of TSTF-359, LCO 3.0.4 and SR 3.0.4 contained a Reviewer's Note which required a plant-specific evaluation and, if necessary, application of specific restrictions on mode changes or Required Actions in individual LCOs. This plant-specific restriction added as a result of the evaluation described in the Reviewer's Note to LCO 3.0.4 is therefore deleted.
In the TSTF mark-ups, STS 3.5.3, "ECCS - Shutdown," an ACTIONS Note is added to indicate that the new LCO 3.0.4b provisions are not applicable to the emergency core cooling system (ECCS) high head subsystem. In the DCPP TS, an ACTIONS Note is added using DCPP-specific terminology of ECCS Centrifugal Charging Pump subsystem.
In the TSTF mark-ups, STS 3.6.9, "Hydrogen Mixing System (HMS)," is modified. DCPP TS do not include this TS, so no changes are needed.
In TS 3.9.1, 'Boron Concentration," the Applicability Note stating, "While this LCO is not met, entry into MODE 6 from MODE 5 is not permitted," is deleted.
Prior to approval of TSTF-359, LCO 3.0.4 and SR 3.0.4 contained a Reviewer's Note which required a plant-specific evaluation and, if necessary, application of specific restrictions on mode changes or Required Actions in individual LCOs. This plant-specific restriction added as a result of the evaluation described in the Reviewer's Note to LCO 3.0.4 is therefore deleted.
2 PG&E Letter DCL-03-118 In TS 3.9.6, 'Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level," the Applicability Note stating, 'While this LCO is not met, entry into a MODE or other specified condition in the Applicability is not permitted,"
is deleted. Prior to approval of TSTF-359, LCO 3.0.4 and-SR 3.0.4 contained a Reviewers Note which required a plant-specific evaluation and, if necessary, application of specific restrictions on mode changes or Required Actions in individual LCOs. This plant-specific restriction added as a result of the evaluation described in the Reviewers Note to LCO 3.0.4 is therefore deleted.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination PG&E has reviewed the proposed no significant hazards consideration determination published in the Federal Register as part of the Consolidated Line-Item Improvement Process. Pacific Gas and Electric Company has concluded that the proposed no significant hazards consideration determination presented in the Federal Register Notice is applicable to Diablo Canyon Power Plant and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).
3.2 Verification and Commitments As discussed in the notice of availability published in the Federal Register on April 4, 2003, for this TS improvement, plant-specific verifications were performed as follows:
PG&E has established TS Bases for LCO 3.0.4 and SR 3.0.4, which state that use of the TS mode change limitation flexibility established by LCO 3.0.4 and SR 3.0.4 is not to be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to operable status before entering an associated mode or other specified condition in the TS Applicability.
The modification also includes changes to the bases for LCO 3.0.4 and SR 3.0.4 that provide details on how to implement the new requirements. The bases changes provide guidance for changing modes or other specified conditions in the Applicability when an LCO is not met. The bases changes describe in detail how: LCO 3.0.4.a allows entry into a mode or other specified condition in the Applicability with the LCO not met when the associated actions to be entered permit continued operation in the mode or other specified condition in the Applicability for an unlimited period of time; LCO 3.0.4.b allows entry into a mode or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of 3
PG&E Letter DCL-03-118 entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; and LCO 3.0.4.c allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a note in the specification, which is typically applied to specifications which describe values and parameters (e.g., Containment Air Temperature, Containment Pressure, MCPR, Moderator Temperature Coefficient), though it may be applied to other specifications based on NRC plant-specific approval. The bases also state that any risk impact should be managed through the program in place to implement 10 CFR 50.65(a)(4) and its implementation guidance, NRC Regulatory Guide 1.182, "Assessing and Managing Risks Before Maintenance Activities at Nuclear Power Plants," and that the results of the risk assessment shall be considered in determining the acceptability of entering the mode or other specified condition in the Applicability, and any corresponding risk management actions. In addition, the bases state that upon entry into a mode or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions for no more than the duration of the applicable Completion Time or until the LCO is met or the unit is not within the Applicability of the TS. The bases also state that SR 3.0.4 does not restrict changing modes or other specified conditions of the Applicability when a surveillance has not been performed within the specified frequency, provided the requirement to declare the LCO not met has been delayed in accordance with SR 3.0.3.
The TS Bases will be revised to reflect the changes to the affected TS and will be implemented in accordance with TS 5.5.14, "Technical Specification (TS) Bases Control Program," as part of the implementation of this amendment, upon NRC approval of this amendment application.
4.0 Environmental Evaluation PG&E has reviewed the environmental evaluation included in the model safety evaluation dated April 4, 2003, as part of the C[IIP. PG&E has concluded that the staffs findings presented in that evaluation are applicable to DCPP and the evaluation is hereby incorporated by reference for this application.
4 PG&E Letter DCL 03-118 Proposed Technical Specification Changes (mark-up)
Remove Paae Insert Paoe 3.0-1 3.0-3 3.1-1 3.3-1 3.3-34 3.3-38 3.4-14 3.4-19 3.4-23 3.4-32 3.4-35 3.5-6 3.6-17 3.7-8 3.7-10 3.8-1 3.9-1 3.9-6 3.0-1 3.0-3 3.1-1 3.3-1 3.3-34 3.3-38 3.4-14 3.4-19 3.4-23 3.4-32 3.4-35 3.5-6 3.6-17 3.7-8 3.7-10 3.8-1 3.9-1 3.9-6 4,
LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.
LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.
LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:
- a. MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />;
- b.
MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and
- c. MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Exceptions to this Specification are stated in the individual Specifications.
Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.
LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.
LCO 3.0.4 When an LCO is not met, entry into a MODE or other specited coendition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified nondition in the Applicability for an unlimited period of time. This LCO 3.0.1 Specification shall not prevent changes iAn
~
MDESor other sperified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the Exceptions to this Specification are stated in the individual Specificaations-.
ICO 3.0.1 is only applicable for entr' in a MODE or other specified co^nd;ition in the Applicability in MODES 1, 2, 3, and 4.
INSERT I --
(continued)
DIABLO CANYON - UNITS 1 & 2 3.0-1 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
Insert I When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:
- a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;
- b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or
- c. When an allowance is stated in the individual value, parameter, or other Specification.
This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR.
Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as "once," the above interval extension does not apply.
If a Completion Time requires periodic performance on a "once per..."
basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this Specification are stated in the individual Specifications.
SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater.
This delay period is permitted to allow performance of the Surveillance.
A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall netonv be made unlesewhen the LCO's Surveillances have been met within their specified Frequenc This provision shall ntry into MODES or other specified conditions i plicability that are required to comply with AC S or that are part of a shutdown of the unit.
INSERT 2 SR 3.0.1 is only applicable for entry into a MODE or other specified condition in the Applicability in MODES 1, 2, 3, and 4.
DIABLO CANYON - UNITS 1 & 2 3.0-3 Unit 1 - Amendment No. 135, 153 Unit 2-Amendment No. 435, 453
Insert 2
, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.
SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)
LCO 3.1.1 SDM shall be within the limits provided in the COLR.
APPLICABILITY:
MODE 2 with keff < 1.0, MODES 3, 4, and 5.
k& tU
-ile this LGQ Os nt met, enNry nto MODE 5 fm MODE 6 Os nt pen;;iJ I C WAhile this LC in
- not mct, cntr'inato MODnEs 5 fromt MODE51 St is not prmtted.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
SDM not within limit.
A.1.
Initiate boration to 15 minutes restore SDM to within limit.
SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limits.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DIABLO CANYON - UNITS 1 & 2 3.1-1 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.1-1.
ACTIONS
-NO)TE Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Enter the Condition Immediately one or more required referenced in channels or trains Table 3.3.1-1 for the inoperable.
channel(s) or trains.
B. One Manual Reactor Trip B. 1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> channel inoperable.
OPERABLE status.
OR B.2 Be in MODE 3.
54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> NOTE While this LCO is not met for function 18, 20 or 21, in MODE 5, making the Rod Control System Gazpable of rod withdrawal is not permitted.
C. One channel or train C.1 Restore channel or train 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable.
to OPERABLE status.
OR C.2.1 Initiate action to fully 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> insert all rods.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.3-1 Unit 1 - Amendment No. 435442 Unit 2 - Amendment No. 435 442
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTIONS N
,nr%-=
u I
~
- 1.
LCO 3.0.4 is not applicable.
- 2.
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Restore required 30 days one required channel channel to OPERABLE inoperable.
status.
B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.8.
met.
C.
NOTE--
C.1 Restore all but one 7 days Not applicable to hydrogen channel to OPERABLE monitor channels.
status.
One or more Functions with two or more required channels inoperable.
D. Two hydrogen monitor D.1 Restore one hydrogen 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> channels inoperable.
monitor channel to OPERABLE status.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.3-34 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System LCO 3.3.4 The Remote Shutdown System Functions in Table 3.3.4-1 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTIONS k IfVFCE I
CI 0 3.0.4 as not applicable.
- 2.
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable.
Function to OPERABLE status.
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 AND Time not met.
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 /> DIABLO CANYON - UNITS 1 & 2 3.3-38 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops-MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.
- 1. All RHR pumps may be removed from operation for
- 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
- a. The core outlet temperature is maintained at least 10F below saturation temperature.
- b.
No operations are permitted that would cause a reduction of the RCS boron concentration; and
- c.
No draining operations to further reduce the RCS water volume are permitted.
- 2.
One RHR loop may be inoperable for < 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided that the other RHR loop is OPERABLE and in operation.
MODE 5 with RCS loops not filled.
~~~~~NOTE W.A.1hile this LCO is not met, entry into MODE 5, Loops Not Filled, from MODE 5, Loops Filled, is not permitted.
APPLICABILITY:
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable.
A.1 Initiate action to restore Immediately RHR loop to OPERABLE status.
B.
Required RHR loops B.1 Suspend all operations Immediately inoperable.
involving reduction in OR RCS boron concentration.
AND No RHR loop in operation.
B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.
DIABLO CANYON - UNITS 1 & 2 3.4-14 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)
LCO 3.4.11 APPLICABILITY:
Each PORV and associated block valve shall be OPERABLE.
MODES 1, 2, and 3.
ACTIONS KI IPCI!
-I'I--J I ~ -
I Separate Condition entry is allowed for each PORV.
- 2.
LCO 3.0.4 iX not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable and capable of power to associated being manually cycled.
block valve.
B.
One PORV inoperable and B.1 Close associated block 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> not capable of being valve.
manually cycled.
AND B.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valve.
AND B.3 Restore the Class I 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> PORV to OPERABLE status.
C.
One block valve inoperable.
NOTE----
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Required Actions do not apply when block valve is inoperable solely as result of complying with Required Actions B.2 or E.3.
C.1 Place associated PORV in manual control.
AND (continued)
DIABLO CANYON - UNITS 1 & 2 3.4-19 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with no safety injection pumps and a maximum of one centrifugal charging pump capable of injecting into the RCS and the accumulators isolated and one of the following pressure relief capabilities:
- a.
Two Class I power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or
- b.
The RCS depressurized and an RCS vent of 2 2.07 square inches.
~~~~~NOTES-
- 1.
Two charging pumps may be made capable of injecting for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pump swap operation.
- 2.
Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
APPLICABILITY:
MODE 4, when any RCS cold leg temperature is
- LTOP arming temperature specified in the PTLR, MODE 5, MODE 6, when the reactor vessel head is on and the vessel head closure bolts are not fully de-tensioned.
ACTIONS 3
ntnic hNOTEnM LCO 3-0-4b is not annficable when enterina MODE 4.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more safety A.1 Initiate action to verify Immediately injection pumps capable of zero safety injection injecting into the RCS.
pumps are capable of injecting into the RCS.
B.
Two centrifugal charging B.1 Initiate action to verify a Immediately pumps capable of injecting maximum of one into the RCS.
centrifugal charging pump is capable of injecting into the RCS.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.4-23 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
RCS Leakage Detection Instrumentation 3.4.15 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:
- a.
Both containment structure sumps and the reactor cavity sump level and flow monitor system,
- b.
One containment atmosphere particulate radioactivity monitor and,
- c.
Either a containment fan cooler unit (CFCU) condensate collection monitor or the containment atmosphere gaseous radioactivity monitor.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS NOTE nCO 2 3.0 is not appircleb-l.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Required containment NOTE--
sump monitors inoperable.
Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
A.1 Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND A.2 Restore required 30 days containment sump monitor to OPERABLE status.
B. Required containment B.1.1 Analyze grab samples of Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> atmosphere particulate the containment radioactivity monitor atmosphere.
OR (continued)
DIABLO CANYON - UNITS 1 & 2 3.4-32 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 APPLICABILITY:
The specific activity of the reactor coolant shall be within limits.
MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) 2 5000F.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
DOSE EQUIVALENT 1-131 NOTE------
specific activity LCO 3.0.4c is rtapplicable.
> 1.0 PCi/gm.
A.1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT 1-131 specific activity within the acceptable region of Figure 3.4.16-1.
AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 specific activity to within limit.
B. Gross specific activity of the B.1 Be in MODE 3 with Tag 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reactor coolant
< 5000F.
100/E pCilgm.
C.
Required Action and C.1 Be in MODE 3 with T,.g 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion to < 5000F.
Time of Condition A not met.
OR DOSE EQUIVALENT 1-131 specific activity in the unacceptable region of Figure 3.4.16-1.
I DIABLO CANYON - UNITS 1 & 2 3.4-35 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.
-------IILJ I r-An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.
APPLICABILITY:
MODE 4.
ACTIONS LC 3
b isnta~
oEC etiua hriguss---t---NOem.-
LCO 3.0.4b is not applicable to ECCS Centrifugal Char-aing Pump subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable.
subsystem to OPERABLE status.
B. Required ECCS B.1 Restore required ECCS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Centrifugal Charging Pump Centrifugal Charging subsystem inoperable.
Pump subsystem to OPERABLE status.
C.
Required Action and C.1 Be in MODE 5.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> associated Completion Time of Condition B not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all equipment In accordance with required to be OPERABLE:
applicable SRs SR 3.5.2.1 SR 3.5.2.7 SR 3.5.2.3 SR 3.5.2.8 SR 3.5.2.4 DIABLO CANYON - UNITS 1 & 2 3.5-6 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
Hydrogen Recombiners 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Hydrogen Recombiners LCO 3.6.8 APPLICABILITY:
Two hydrogen recombiners shall be OPERABLE.
MODES 1 and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One hydrogen recombiner A.1 NOTE inoperable.
LCO 3.0.4 is not applicable.
Restore hydrogen 30 days recombiner to OPERABLE status.
B. Two hydrogen recombiners B.1 Verify by administrative 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.
means that the hydrogen AND control function is maintained.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND thereafter B.2 Restore one hydrogen 7 days recombiner to OPERABLE status.
C.
Required Action and C.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.
DIABLO CANYON - UNITS 1 & 2 3.6-17 Unit 1 - Amendment No. 43&
Unit 2 - Amendment No. 435
ADVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 10% Atmospheric Dump Valves (ADVs)
LCO 3.7.4 APPLICABILITY:
Four ADV lines shall be OPERABLE.
MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One required ADV line A.1 inoperable.
LCO 3.0.1 is not applirable Restore required ADV line 7 days to OPERABLE status B. Two required ADV lines B.1 Restore at least one ADV 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.
line to OPERABLE status.
C.
Three or more required C.1 Restore at least two ADV 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ADV lines inoperable.
lines to OPERABLE status.
D. Required Action and D.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 AND Time not met.
D.2 Be in MODE 4 without 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> reliance upon steam generator for heat removal.
DIABLO CANYON - UNITS 1 & 2 3.7-8 Unit 1 - Amendment No. U3S Unit 2 - Amendment No. 135
AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be OPERABLE.
-NOTE.
Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.
APPLICABILITY:
MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS LCO 3.0.4b is not applicable.
r-t CONDITION REQUIRED ACTION COMPLETION TIME A.
One steam supply to A. 1 Restore steam supply to 7 days turbine driven AFW pump OPERABLE status.
AND 10 days from discovery of failure to meet the LCO B. One AFW train inoperable B.1 Restore AFW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in MODE 1, 2 or 3 for OPERABLE status.
reasons other than AND Condition A.
10 days from discovery of failure to meet the LCO C. Required Action and C.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 AND Time for Condition A or B not met.
C.2 Be in MODE 4.
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> OR Two AFW trains inoperable in MODE 1, 2 or 3.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.7-10 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:
- a.
Two qualified circuits between the offsite transmission network and the onsite Class 1 E AC Electrical Power Distribution System; and
- b.
Three diesel generators (DGs) capable of supplying the onsite Class 1 E power distribution subsystem(s); and
- c.
Two supply trains of the diesel fuel oil (DFO) transfer system.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS L O 0
b i n t D i b
t-o N Us I LCO 3.0.4b is not applicable to DGs.
t CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.
required OPERABLE AND offsite circuit.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
AND A.2 Restore required offsite 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> circuit to OPERABLE AND status.
A 10 days from discovery of failure to meet LCO.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.8-1 Unit I - Amendment No. 435 Unit 2-Amendment No. 435
Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 APPLICABILITY:
Boron concentrations of all filled portions of the Reactor Coolant System, the refueling canal, and the refueling cavity, that have direct access to the reactor vessel, shall be maintained within the limit specified in the COLR.
MODE 6 NOTE Mhile thie IGC ic not mc tr, ;rt y into MODE 6 frm MODE 6 Os not peittdL.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Boron concentration not A.1 Suspend CORE Immediately within limit.
ALTERATIONS.
AND A.2 Suspend positive Immediately reactivity additions.
AND A.3 Initiate action to restore Immediately boron concentration to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> specified in COLR.
d DIABLO CANYON - UNITS 1 & 2 3.9-1 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
RHR and Coolant Circulation - Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.
APPLICABILITY:
MODE 6 with the water level < 23 ft above the top of reactor vessel flange.
NOTE While this LCO is not met, entry into a MODE or other specified condition in the APPLICABILITY ie not permited.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE.
OPERABLE status.
OR A.2 Initiate action to Immediately establish 2 23 ft of water above the top of reactor vessel flange.
B. No RHR loop in operation.
B.1 Suspend operations Immediately involving a reduction in reactor coolant boron concentration.
AND B.2 Initiate action to restore Immediately one RHR loop to operation.
AND B.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.
DIABLO CANYON - UNITS 1 & 2 3.9-6 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 4W PG&E Letter DCL 03-118 Proposed Technical Specification Changes (retyped)
LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.
LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.
If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.
LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to place the unit, as applicable, in:
- a.
MODE 3 within 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />;
- b.
MODE 4 within 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />; and
- c.
MODE 5 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />.
Exceptions to this Specification are stated in the individual Specifications.
Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.
LCO 3.0.3 is only applicable in MODES 1, 2, 3, and 4.
LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:
- a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;
- b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or
- c.
When an allowance is stated in the individual value, parameter, or other Specification.
This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.0-1 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
LCO Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR.
Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.
SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as "once," the above interval extension does not apply.
If a Completion Time requires periodic performance on a "once per..."
basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this Specification are stated in the individual Specifications.
SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up to the limit of the specified Frequency, whichever is greater.
This delay period is permitted to allow performance of the Surveillance.
A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the risk impact shall be managed.
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3.
When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
DIABLO CANYON - UNITS 1 & 2 3.0-3 Unit I - Amendment No. 135, 153 Unit 2-Amendment No. 135, 153
SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)
LCO 3.1.1 SDM shall be within the limits provided in the COLR.
APPLICABILITY:
MODE 2 with kf < 1.0, MODES 3, 4, and 5.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
SDM not within limit.
A.1.
Initiate boration to 15 minutes restore SDM to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limits.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> DIABLO CANYON - UNITS 1 & 2 3.1-1 Unit I - Amendment No. 435 Unit 2 - Amendment No. 435
RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.
APPLICABILITY:
ACTIONS According to Table 3.3.1-1.
Spa Cntn--NOTEr is ac t
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Enter the Condition Immediately one or more required referenced in channels or trains Table 3.3.1-1 for the inoperable.
channel(s) or trains.
B. One Manual Reactor Trip B.1 Restore channel to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> channel inoperable.
OPERABLE status.
OR B.2 Be in MODE 3.
54 hours6.25e-4 days <br />0.015 hours <br />8.928571e-5 weeks <br />2.0547e-5 months <br /> C. One channel or train C. 1 Restore channel or train 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> inoperable.
to OPERABLE status.
OR C.2.1 Initiate action to fully 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> insert all rods.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.3-1 Unit 1 - Amendment No. 435 442 Unit 2 - Amendment No. 435 442
PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 APPLICABILITY:
The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.
MODES 1, 2 and 3.
ACTIONS Separate Co dto nr salo NOTE.
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Restore required 30 days one required channel channel to OPERABLE inoperable.
status.
B. Required Action and B.1 Initiate action in Immediately associated Completion accordance with Time of Condition A not Specification 5.6.8.
met.
C. --
NOTE----
C.1 Restore all but one 7 days Not applicable to hydrogen channel to OPERABLE monitor channels.
status.
One or more Functions with two or more required channels inoperable.
D. Two hydrogen monitor D.1 Restore one hydrogen 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> channels inoperable.
monitor channel to OPERABLE status.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.3-34 Unit 1 - Amendment No. 135 Unit 2 - Amendment No. 43
Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION 3.3.4 Remote Shutdown System LCO 3.3.4 The Remote Shutdown System Functions in Table 3.3.4-1 shall be OPERABLE.
APPLICABILITY:
MODES 1, 2 and 3.
ACTIONS Ll^TCr!!
I i::
~
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable.
Function to OPERABLE status.
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 AND Time not met.
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 /> DIABLO CANYON - UNITS 1 & 2 3.3-38 Unit I - Amendment No. 435 Unit 2 - Amendment No. 435
RCS Loops - MODE 5, Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 RCS Loops-MODE 5, Loops Not Filled LCO 3.4.8 Two residual heat removal (RHR) loops shall be OPERABLE and one RHR loop shall be in operation.
L IfriTe'
tJ I r-.%
- 1. All RHR pumps may be removed from operation for
- 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> provided:
- a.
The core outlet temperature is maintained at least 10F below saturation temperature.
- b.
No operations are permitted that would cause a reduction of the RCS boron concentration; and
- c.
No draining operations to further reduce the RCS water volume are permitted.
- 2.
One RHR loop may be inoperable for
- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided that the other RHR loop is OPERABLE and in operation.
APPLICABILITY:
MODE 5 with RCS loops not filled.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR loop inoperable.
A.1 Initiate action to restore Immediately RHR loop to OPERABLE status.
B. Required RHR loops B.1 Suspend all operations Immediately inoperable.
involving reduction in OR RCS boron concentration.
AND No RHR loop in operation.
B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.
DIABLO CANYON - UNITS 1 & 2 3.4-14 Unit 1 - Amendment No. 436 Unit 2 - Amendment No. 45
Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.11 Pressurizer Power Operated Relief Valves (PORVs)
LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS S e t t a f--r NOTE--
Separate Condition entry is allowed for each POWV CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable and capable of power to associated being manually cycled.
block valve.
B.
One PORV inoperable and B. 1 Close associated block 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> not capable of being valve.
manually cycled.
AND B.2 Remove power from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated block valve.
AND B.3 Restore the Class I 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> PORV to OPERABLE status.
C.
One block valve inoperable.
NOTE-1 hour Required Actions do not apply when block valve is inoperable solely as result of complying with Required Actions B.2 or E.3.
C. 1 Place associated PORV in manual control.
AND (continued)
DIABLO CANYON - UNITS I & 2 3.4-19 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 436
LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with no safety injection pumps and a maximum of one centrifugal charging pump capable of injecting into the RCS and the accumulators isolated and one of the following pressure relief capabilities:
- a.
Two Class I power operated relief valves (PORVs) with lift settings within the limits specified in the PTLR, or
- b.
The RCS depressurized and an RCS vent of 2 2.07 square inches.
nv
- 1.
Two charging pumps may be made capable of injecting for < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for pump swap operation.
- 2.
Accumulator may be unisolated when accumulator pressure is less than the maximum RCS pressure for the existing RCS cold leg temperature allowed by the P/T limit curves provided in the PTLR.
APPLICABILITY:
MODE 4, when any RCS cold leg temperature is
- LTOP arming temperature specified in the PTLR, MODE 5, MODE 6, when the reactor vessel head is on and the vessel head closure bolts are not fully de-tensioned.
ACTIONS N
L I I r- ____
LCO 3.0.4b is not applicable when entering MODE 4.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more safety A.1 Initiate action to verify Immediately injection pumps capable of zero safety injection injecting into the RCS.
pumps are capable of injecting into the RCS.
B.
Two centrifugal charging B.1 Initiate action to verify a Immediately pumps capable of injecting maximum of one into the RCS.
centrifugal charging pump is capable of injecting into the RCS.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.4-23 Unit I - Amendment No. 435 Unit 2 - Amendment No. 435
RCS Leakage Detection Instrumentation 3.4.15 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:
- a.
Both containment structure sumps and the reactor cavity sump level and flow monitor system,
- b.
One containment atmosphere particulate radioactivity monitor and,
- c.
Either a containment fan cooler unit (CFCU) condensate collection monitor or the containment atmosphere gaseous radioactivity monitor.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required containment NOTED sump monitors inoperable.
Not required until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishment of steady state operation.
A.1 Perform SR 3.4.13.1.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND A.2 Restore required 30 days containment sump monitor to OPERABLE status.
B. Required containment B. 1.1 Analyze grab samples of Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> atmosphere particulate the containment radioactivity monitor atmosphere.
OR (continued)
I DIABLO CANYON - UNITS 1 & 2 3.4-32 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 APPLICABILITY:
The specific activity of the reactor coolant shall be within limits.
MODES 1 and 2, MODE 3 with RCS average temperature (Tag) 2 5000F.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
DOSE EQUIVALENT 1-131 NOTE----
specific activity LCO 3.0.4c is applicable.
> 1.0 pCi/gm.
A.1 Verify DOSE Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> EQUIVALENT 1-131 specific activity within the acceptable region of Figure 3.4.16-1.
AND A.2 Restore DOSE 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> EQUIVALENT 1-131 specific activity to within limit.
B. Gross specific activity of the B. I Be in MODE 3 with T.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> reactor coolant
< 5000F.
100/E pCi/gm.
C. Required Action and C.1 Be in MODE 3 with Tag 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion to < 500¶F.
Time of Condition A not met.
OR DOSE EQUIVALENT 1-131 specific activity in the unacceptable region of Figure 3.4.16-1.
DIABLO CANYON - UNITS 1 & 2 3.4-35 Unit 1 - Amendment No. 436 Unit 2 - Amendment No.435
ECCS - Shutdown 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.3 ECCS - Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.
L111U
[ML i I An RHR train may be considered OPERABLE during alignment and operation for decay heat removal, if capable of being manually realigned to the ECCS mode of operation.
APPLICABILITY:
MODE 4.
ACTIONS LC-b is notpCn OTE----
n g
LCO 3.0.4b is not applicable to ECCS Centrifugal Charging Pump subsystem.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Required ECCS residual A.1 Initiate action to restore Immediately heat removal (RHR) required ECCS RHR subsystem inoperable.
subsystem to OPERABLE status.
B. Required ECCS B.1 Restore required ECCS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Centrifugal Charging Pump Centrifugal Charging subsystem inoperable.
Pump subsystem to OPERABLE status.
C.
Required Action and C.1 Be in MODE 5.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> associated Completion Time of Condition B not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all equipment In accordance with required to be OPERABLE:
applicable SRs SR 3.5.2.1 SR 3.5.2.7 SR 3.5.2.3 SR 3.5.2.8 SR 3.5.2.4 DIABLO CANYON - UNITS 1 & 2 3.5-6 Unit I - Amendment No. 435 Unit 2 - Amendment No. 435
Hydrogen Recombiners 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 Hydrogen Recombiners LCO 3.6.8 Two hydrogen recombiners shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One hydrogen recombiner A.1 Restore hydrogen 30 days inoperable.
recombiner to OPERABLE status.
B. Two hydrogen recombiners B.1 Verify by administrative 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.
means that the hydrogen AND control function is maintained.
Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND thereafter B.2 Restore one hydrogen 7 days recombiner to OPERABLE status.
C.
Required Action and C.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.
I DIABLO CANYON - UNITS I & 2 3.6-17 Unit 1 - Amendment No. 435 Unit 2-Amendment No. 435
ADVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 10% Atmospheric Dump Valves (ADVs)
LCO 3.7.4 Four ADV lines shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required ADV line A.1 Restore required ADV line 7 days inoperable.
to OPERABLE status B. Two required ADV lines B.1 Restore at least one ADV 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.
line to OPERABLE status.
C.
Three or more required C.1 Restore at least two ADV 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ADV lines inoperable.
lines to OPERABLE status.
D. Required Action and D.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 AND Time not met.
D.2 Be in MODE 4 without 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> reliance upon steam generator for heat removal.
I DIABLO CANYON - UNITS 1 & 2 3.7-8 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
AFW System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AFV) System LCO 3.7.5 Three AFW trains shall be OPERABLE.
--- NOTE------
Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.
APPLICABILITY:
MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACTIONS
-NOTE-LCO 3.0.4b is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One steam supply to A. 1 Restore steam supply to 7 days turbine driven AFW pump OPERABLE status.
AND 10 days from discovery of failure to meet the LCO B.
One AFW train inoperable B.1 Restore AFW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in MODE 1, 2 or 3 for OPERABLE status.
reasons other than AND Condition A.
10 days from discovery of failure to meet the LCO C.
Required Action and C.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 AND Time for Condition A or B AND not met.
C.2 Be in MODE 4.
18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> OR Two AFW trains inoperable in MODE 1, 2 or 3.
(continued)
DIABLO CANYON - UNITS 1 & 2 3.7-10 Unit 1 - Amendment No. 413 Unit 2 - Amendment No. 435
AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical sources shall be OPERABLE:
- a.
Two qualified circuits between the offsite transmission network and the onsite Class 1 E AC Electrical Power Distribution System; and
- b.
Three diesel generators (DGs) capable of supplying the onsite Class I E power distribution subsystem(s); and
- c.
Two supply trains of the diesel fuel oil (DFO) transfer system.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS L eI^EC NU~~~~~~~~~~~~~~~~~~~~~
I ff-
LCO 3.0.4b is not applicable to DGs.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable.
required OPERABLE AND offsite circuit.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
AND A.2 Restore required offsite 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> circuit to OPERABLE AND status.
A 10 days from discovery of failure to meet LCO.
(continued)
DIABLO CANYON - UNITS I & 2 3.8-1 Unit 1 - Amendment No. 435 Unit 2 - Amendment No. 435
Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Boron Concentration LCO 3.9.1 Boron concentrations of all filled portions of the Reactor Coolant System, the refueling canal, and the refueling cavity, that have direct access to the reactor vessel, shall be maintained within the limit specified in the COLR.
APPLICABILITY:
MODE 6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Boron concentration not A.1 Suspend CORE Immediately within limit.
ALTERATIONS.
AND A.2 Suspend positive Immediately reactivity additions.
AND A.3 Initiate action to restore Immediately boron concentration to within limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Verify boron concentration is within the limit 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> specified in COLR.
DIABLO CANYON - UNITS 1 & 2 3.9-1 Unit 1 - Amendment No. 435 Unit 2 - Amendment No.45
RHR and Coolant Circulation - Low Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE, and one RHR loop shall be in operation.
APPLICABILITY:
MODE 6 with the water level < 23 ft above the top of reactor vessel flange.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Less than the required A.1 Initiate action to restore Immediately number of RHR loops required RHR loops to OPERABLE.
OPERABLE status.
OR A.2 Initiate action to Immediately establish 2 23 ft of water above the top of reactor vessel flange.
B. No RHR loop in operation.
B.1 Suspend operations Immediately involving a reduction in reactor coolant boron concentration.
AND B.2 Initiate action to restore Immediately one RHR loop to operation.
AND B.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> penetrations providing direct access from containment atmosphere to outside atmosphere.
DIABLO CANYON - UNITS 1 & 2 3.9-6 Unit 1 - Amendment No. 135 Unit 2 - Amendment No. 135 PG&E Letter DCL 03-118 Changes to Technical Specification Bases Pages (For information only)
LCO Applicability B 3.0 BASES LCO 3.0.3 (continued)
In MODES 1, 2, 3, and 4, LCO 3.0.3 provides actions for Conditions not covered in other Specifications. The requirements of LCO 3.0.3 do not apply in MODES 5 and 6 because the unit is already in the most restrictive Condition required by LCO 3.0.3. The requirements of LCO 3.0.3 do not apply in other specified conditions of the Applicability (unless in MODE 1, 2, 3, or 4) because the ACTIONS of individual Specifications sufficiently define the remedial measures to be taken.
Exceptions to LCO 3.0.3 are provided in instances where requiring a unit shutdown, in accordance with LCO 3.0.3, would not provide appropriate remedial measures for the associated condition of the unit.
An example of this is in LCO 3.7.15, "Fuel Storage Pool Water Level."
LCO 3.7.15 has an Applicability of "During movement of irradiated fuel assemblies in the fuel storage pool." Therefore, this LCO can be applicable in any or all MODES. If the LCO and the Required Actions of LCO 3.7.15 are not met while in MODE 1, 2, 3, or 4, there is no safety benefit to be gained by placing the unit in a shutdown condition.
The Required Action of LCO 3.7.15 of "Suspend movement of irradiated fuel assemblies in the fuel storage pool" is the appropriate Required Action to complete in lieu of the ACTIONS of LCO 3.0.3.
These exceptions are addressed in the individual Specifications.
GQ-3.0.4 A,
- _ * *rv_
__ _.s __
LC6 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability %when an IC i Os not metd It precludes placing the unit in a MODE or other specified condition stated in that Applicability (e.g., Applicability dsired to be entered) when the following exist:
- a. Unit conditions are such that the requirements of the LCO would not be met in the Apolicability desired to be entered: and INSERT 3-*
a_
A__
A! _
_ j fl 1cauniflt-mlc-1 noconmncwitf tfC L=UW regOrr~mnRTS. !T Me-Applicability were cntered, would result in the unit beiRn required to exit the Applicability desired to be entered to comply with the Required Actions.
Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE chandge. Therefore, in such cases, entr; into a MODE or other specified condition in the Applicability may be made in aoree-danse ith the provisions of the Required Actions. Th p rin of this Specification should not be interpreted as endo-rsing the failure to exercise the good practice of restori OPERABLE status before entering-an-specified condition in the Applicability.
ng systems or components to as-ociated M
_D or thr (continued)
DIABLO CANYON
- UNITS I & 2 B 3.0-4 R~~~~~~~~~~Ievision 1i DIABLO CANYON - UNITS I & 2 B 3.0-4 Revision 1
LCO Applicability B 3.0 LGQ-O 3A (GGAtined)
T;he provisions of LCO 3.0.4 shall not prevent changcs in MODES or other specified ronditions ir the Applicability that ar rrequired to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not preveRt haRges irn MODES or other specified oGRditieRs in the Applicability that result from any unit shutdown.
Exceptions to LCO 3.0.4 are stated in the individual Specifications.
These exceptione allow entr,' ieto MODES or otheFr specAicd coRditinrs in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited peod of time.
Exceptions may apply to all the ACTIONS or to a specific Required A~ntiR of a Specification.
IO 3.
4 i only applicable.heRn entering MODrE 4 fom M ODE 5, MODE 3 from MODE 4, MODE 2 from MODE 3, or MODE I from MODE 2. Furthermore, Irn 3.0.4 is applicable h
any other specified condition in the Applicability only while operating in MODE 1, 2, 3, or 4. The requirements of LCO 3.0.4 do not apply MODES 5 and 6, or in other specified conditions of the Applicability (unless in MODES 1, 2, 3, or 4) because the ACTIONS of ini.idual Specifications sufficiently define the remedial measures to be taken. In some eases (e.g., where a review has concIuded that specif restriction on MODE changes should be included) these ACTIONS provide a Note that state- 'While this LCO is not mnt, enr' i nto a MODE or other specified condition in the Applicability iE not permitted, unless required to comply with ACTIONS." This Note i6 a requirement explicitly precluding entry into a MODE or other specified condition ot thc Applicabit.
Surmeillances do not have to be peaormed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Theeforfe, rhanging MODES or other specified conditions while in an ACTIONS Condition, in compliance with LCO 3.0.1 or whe n ex tion to LC 3.0.4 is stated, is not a violation SR 3.0.1 oSR R 3.0.1 for those Sur'eillances that do not have to be pe~foemed due to the associated inprabe jqipment. However, SRs-mrust be met to ensu,OPER=ABILITY pro to d.,laring thea6sociated equipment OPERABLE (or variable within limits) and restoring 6omelian-e with the affected ICr.
(continued)
DIABLO CANYON - UNITS I & 2 B 3.0-5 Revision I
Insert 3 LCO 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when an LCO is not met. It allows placing the unit in a MODE or other specified condition stated in that Applicability (e.g., the Applicability desired to be entered) when unit conditions are such that the requirements of the LCO would not be met, in accordance with LCO 3.0.4.a, LCO 3.0.4.b, or LCO 3.0.4.c.
LCO 3.0.4.a allows entry into a MODE or other specified condition in the Applicability with the LCO not met when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. Compliance with Required Actions that permit continued operation of the unit for an unlimited period of time in a MODE or other specified condition provides an acceptable level of safety for continued operation. This is without regard to the status of the unit before or after the MODE change. Therefore, in such cases, entry into a MODE or other specified condition in the Applicability may be made in accordance with the provisions of the Required Actions.
LCO 3.0.4.b allows entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate.
The risk assessment may use quantitative, qualitative, or blended approaches, and the risk assessment will be conducted using the plant program, procedures, and criteria in place to implement 10 CFR 50.65(a)(4), which requires that risk impacts of maintenance activities to be assessed and managed. The risk assessment, for the purposes of LCO 3.0.4 (b), must take into account all inoperable Technical Specification equipment regardless of whether the equipment is included in the normal 10 CFR 50.65(a)(4) risk assessment scope. The risk assessments will be conducted using the procedures and guidance endorsed by Regulatory Guide 1.182, "Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants." Regulatory Guide 1.182 endorses the guidance in Section 11 of NUMARC 93-01, 'Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." These documents address general guidance for conduct of the risk assessment, quantitative and qualitative guidelines for establishing risk management actions, and example risk management actions. These include actions to plan and conduct other activities in a manner that controls overall risk, increased risk awareness by shift and management personnel, actions to reduce the duration of the condition, actions to minimize the magnitude of risk increases (establishment of backup success paths or compensatory measures), and determination that the proposed MODE change is acceptable. Consideration should also be given to the probability of completing restoration such that the requirements of the LCO would be met prior to the expiration of ACTIONS Completion Times that would require exiting the Applicability.
LCO 3.0.4.b may be used with single, or multiple systems and components unavailable.
NUMARC 93-01 provides guidance relative to consideration of simultaneous unavailability of multiple systems and components.
Insert 3 (cont'd)
The results of the risk assessment shall be considered in determining the acceptability of entering the MODE or other specified condition in the Applicability, and any corresponding risk management actions.
The Technical Specifications allow continued operation with equipment unavailable in MODE 1 for the duration of the Completion Time. Since this is allowable, and since in general the risk impact in that particular MODE bounds the risk of transitioning into and through the applicable MODES or other specified conditions in the Applicability of the LCO, the use of the LCO 3.0.4.b allowance should be generally acceptable, as long as the risk is assessed and managed as stated above. However, there is a small subset of systems and components that have been determined to be more important to risk and use of the LCO 3.0.4.b allowance is prohibited. The LCOs governing these systems and components contain Notes prohibiting the use of LCO 3.0.4.b by stating that LCO 3.0.4.b is not applicable.
LCO 3.0.4.c allows entry into a MODE or other specified condition in the Applicability with the LCO not met based on a Note in the Specification which states LCO 3.0.4.c is applicable. These specific allowances permit entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered do not provide for continued operation for an unlimited period of time and a risk assessment has not been performed. This allowance may apply to all the ACTIONS or to a specific Required Action of a Specification. The risk assessments performed to justify the use of LCO 3.0.4.b usually only consider systems and components. For this reason, LCO 3.0.4.c is typically applied to Specifications which describe values and parameters (e.g.,
Containment Air Temperature, Containment Pressure, MCPR, Moderator Temperature Coefficient), and may be applied to other Specifications based on NRC plant-specific approval.
The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.
The provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of LCO 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that results from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE I to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.
Upon entry into a MODE or other specified condition in the Applicability with the LCO not met, LCO 3.0.1 and LCO 3.0.2 require entry into the applicable Conditions and Required Actions until the Condition is resolved, until the LCO is met, or until the unit is not within the Applicability of the Technical Specification.
Surveillances do not have to be performed on the associated inoperable equipment (or on variables outside the specified limits), as permitted by SR 3.0.1. Therefore, utilizing LCO 3.0.4 is not a violation of SR 3.0.1 or SR 3.0.4 for any Surveillances that have not
Insert 3 (cont'd) been performed on inoperable equipment. However, SRs must be met to ensure OPERABILITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.
SR Applicability B 3.0 BASES (continued)
SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applir~abiiy This Specfition ensures that system and ceom onent OPERABILITY requirements and variable limits arc met before entry into MODES or other specified conditions in the Applicability for which these systems O
xesrr--
so
-- f-rsrt;rf tho- *s;#
INSERT 4-*
L AW The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good prartice of restering Syrtemn or component to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.
Howeyer, in Gertair circGumStanGes, failing to meet an SR will not resulte in SR 3.0.4 restricting a MODE change or other specified condition change. When a sy,'stem, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 3.0.1, which states that surweillances do not have to be performed on inoperable equipment.
When equipment Is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) to be performed is removed. Therefore, failing to perform the Surveillance(s) within the specrified FCrequency does not result in an SR 3.0.4 restriction to changing MODES or other specified conditions of the Applicability.
However, since the !LC is not met in this instanee, LCO 3.0.1 will govern any reStrictions that may (or may not) apply to MODE or other sperified conditien Ghanges.
The provisions of SR 3.0.1 shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 3.0.1 shall not prvent crhanges Oin MODES or other sperified conditions in the Applicability that result from any unit shudown The precise requimrments for performanre of SRAr are sperified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and onditions necessary fo m tn t SRs are speified iR the Frequency, in the Surveillance, or both. This allows performance of Suervellances when the prerequisite conditioR(s) specified in a Surveillanre procedure require entry into the MODE or other specified (Gontinued)
DIABLO CANYON - UNITS 1 & 2 B 3.0-13 Revision I
SR Applicability B 3.0 BASES SRR 34 (Getined) cond{tion in the Applicability of the asSociated LCO pIrio to the peformance or completion of a Surveillance. A Suryeillance that could not bc perFormed until after entering the LCO Applicability, would have its Frequency specified such that it ie not "du c" u til the specific conditions needed are met. Altemately, the Surweillance may be stated in the form of a Note as not required (to be met or peofbmed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4,.Frequen.y SR 3.0.4 is only applicable when entering MODE 4 from MODE 5, MODE 3 from MODE 4, Mode 2 from MODE 3, or D.,f MODE
- 2. Furthermore, SR 3.0.1 is applicable when entering any other pe ra^fied G^renit;on in theAplihility ery w lh ile operating iR MODES 4, 2 3, eF4.
The requirements of SR 3.0.1 do not apply in MODES 5 and 6, or in other specified conditiose of the Applicability (unless in MODES 1, 2, 3, or 1) because the ACTIONS of individual Specifications sufficiently define the remedial measures to be taken.
DIABLO CANYON - UNITS I & 2 B 3.0-14 Revision 1
Insert 4 SR 3.0.4 establishes the requirement that all applicable SRs must be met before entry into a MODE or other specified condition in the Applicability.
This Specification ensures that system and component OPERABILITY requirements and variable limits are met before entry into MODES or other specified conditions in the Applicability for which these systems and components ensure safe operation of the unit.
The provisions of this Specification should not be interpreted as endorsing the failure to exercise the good practice of restoring systems or components to OPERABLE status before entering an associated MODE or other specified condition in the Applicability.
A provision is included to allow entry into a MODE or other specified condition in the Applicability when an LCO is not met due to a Surveillance not being met in accordance with LCO 3.0.4.
However, in certain circumstances, failing to meet an SR will not result in SR 3.0.4 restricting a MODE change or other specified condition change. When a system, subsystem, division, component, device, or variable is inoperable or outside its specified limits, the associated SR(s) are not required to be performed, per SR 3.0.1, which states that surveillances do not have to be performed on inoperable equipment. When equipment is inoperable, SR 3.0.4 does not apply to the associated SR(s) since the requirement for the SR(s) does not result in an SR 3.0.4 restriction to changing MODES or other specified conditions of the Applicability. However, since the LCO is not met in this instance, LCO 3.0.4 will govern any restrictions that may (or may not) apply to MODE or other specified condition changes. SR 3.0.4 does not restrict changing MODES or other specified conditions of the Applicability when a Surveillance has not been performed within the specified Frequency, provided that requirement to declare the LCO not met has been delayed in accordance with SR 3.0.3.
The provisions of SR 3.0.4 shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS. In addition, the provisions of SR 3.0.4 shall not prevent changes in MODES or other specified conditions in the Applicability that result from any unit shutdown. In this context, a unit shutdown is defined as a change in MODE or other specified condition in the Applicability associated with transitioning from MODE 1 to MODE 2, MODE 2 to MODE 3, MODE 3 to MODE 4, and MODE 4 to MODE 5.
The precise requirements for performance of SRs are specified such that exceptions to SR 3.0.4 are not necessary. The specific time frames and conditions necessary for meeting the SRs are specified in the Frequency, in the Surveillance, or both. This allows performance of Surveillances when the prerequisite condition(s) specified in a Surveillance procedure require entry into the MODE or other specified condition in the Applicability of the associated LCO prior to the performance or completion of a Surveillance. A Surveillance that could not be performed until after entering the LCO's Applicability, would have its Frequency specified such that it is not udue" until the specific conditions needed are met. Alternately, the Surveillance may be stated in the form of a Note, as not required (to be met or performed) until a particular event, condition, or time has been reached. Further discussion of the specific formats of SRs' annotation is found in Section 1.4, Frequency.
RTS Instrumentation B 3.3.1 BASES ACTIONS C.1, C.2.1. and C.2.2 (continued) incapable of rod withdrawal within the next hour (e.g., by de-energizing all CRDMs, by opening the RTBs, or by de-energizing the motor generator (MG) sets). The additional hour for the latter provides sufficient time to accomplish the action in an orderly manner. With the rods fully inserted and the Rod Control System rendered incapable of rod withdrawal, these Functions are no longer required.
The Completion Time is reasonable considering that in this Condition, the remaining OPERABLE train is adequate to perform the safety function, and given the low probability of an event occurring during this interval.
Condition C is modified by a Note stating that while this LCO is not met for Funrtione 19, 20, Or 21 in MAODE 5 making the Rod Control Syestem capable of rod withdrawal is not permitted. This note i; in addition to the requirements of LCO 3.0.4 which preclude the transition from either MODE 3 or MODE 4 to MODE 3 or MODE 4 with the Rod control System capable of rod withdrawal or all rods not fully inserted for R u-ntin 1IO. 20, or 21 with one channel or train inoRpeable.
D.1.1. D.1.2. D.2.1. D.2.2. and D.3 Condition D applies to the Power Range Neutron Flux-High Function.
The NIS power range detectors provide input to the Rod Control System and, therefore, have a two-out-of-four trip logic. A known inoperable channel must be placed in the tripped condition. This results in a partial trip condition requiring only one-out-of-three logic for actuation. The 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> allowed to place the inoperable channel in the tripped condition is justified in WCAP-10271-P-A (Ref. 7).
In addition to placing the inoperable channel in the tripped condition, THERMAL POWER must be reduced to
- 75% RTP within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Reducing the power level prevents operation of the core with radial power distributions beyond the design limits. With one of the NIS power range detectors inoperable, 1/4 of the radial power distribution monitoring capability is lost.
As an alternative to the above actions, the inoperable channel can be placed in the tripped condition within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and the QPTR monitored once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> as per SR 3.2.4.2, including the SR 3.2.4.2 note, for QPTR verification. Calculating QPTR every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> compensates for the lost monitoring capability due to the inoperable NIS power range channel and allows continued unit operation at power levels > 75%
RTP. The 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Completion Time and the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency are consistent with LCO 3.2.4, "QUADRANT POWER TILT RATIO (QPTR)."
(continued)
DIABLO CANYON - UNITS 1 & 2
PAM Instrumentation B 3.3.3 BASES (continued)
ACTIONS Note 1 has bcen added in the ACTIONS to exclude the MODE change restriction of LCO 3.0.4. This exception allows entry into the applicable MODE while relying on the ACTIONS even though the ACTIONS may eventually require unit shutdown. This exception is acreptable due to the passive function of the instruments, the operators ability to respond to an accGidenrt using alternate instruments and methods, and the low probability of an event requiring these instruments.
A Note 2-has been added in the ACTIONS to clarify the application of Completion Time rules. The Conditions of this Specification may be entered independently for each Function listed on Table 3.3.3-1. When the required channels in Table 3.3.3-1 are specified on a per steam generator basis, then the Condition may be entered separately for each steam generator.
The Completion Time(s) of the inoperable channel(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.
A.1 Condition A applies when one or more Functions have one required channel that is inoperable. Required Action A.1 requires restoring the inoperable channel to OPERABLE status within 30 days. The 30 day Completion Time is based on operating experience and takes into account the remaining OPERABLE channel (or in the case of a Function that has only one required channel, other non-Regulatory Guide 1.97 instrument channels to monitor the Function), the passive nature of the instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event requiring PAM instrumentation during this interval.
B. 1 Condition B applies when the Required Action and associated Completion Time for Condition A are not met. This Required Action specifies immediate initiation of actions in Specification 5.6.8, which requires a written report to be submitted to the NRC. This report discusses the results of the root cause evaluation of the inoperability and identifies proposed restorative actions. This action is appropriate in lieu of a shutdown requirement since alternative actions are identified before loss of functional capability, and given the likelihood of unit conditions that would require information provided by this instrumentation.
(continued)
DIABLO CANYON - UNITS 1 & 2 B 3.0-119 Revision 1
Remote Shutdown System B 3.3.4 BASES (continued)
APPLICABILITY The Remote Shutdown System LCO is applicable in MODES 1, 2, and 3. This is required so that the unit can be placed and maintained in MODE 3 for an extended period of time from a location other than the control room until either control is transferred back to the control room or a cooldown is initiated.
This LCO is not applicable in MODE 4, 5, or 6. In these MODES, the facility is already subcritical and in a condition of reduced RCS energy.
Under these conditions, considerable time is available to restore necessary instrument control functions if control room instruments or controls become unavailable.
ACTIONS Note 1 is included which excludes the MODE change restriction ot LCO 3.0.4. Thie eXccption allows entry into an applicable MODE while relying on the ACTIONS even though the ACTIONS may eventually require a unit shutdown. TThis exception is acceptable due to the low probability of an event requiring the Remnotc Shutdown System and b
uea 1 _
them etionrnt c-an aeerallr be repairdi dring Pcraton
-. __._.._- aA-Whi. I-..
r
-- w-Ad---lA r -M-l g-without significant risk of spurious trip.
A Note 2-has been added to the ACTIONS to clarify the application of Completion Time rules. Separate Condition entry is allowed for each Function listed on Table 3.3.4-1. The Completion Time(s) of the inoperable channel(s)Itrain(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.
A.l Condition A addresses the situation where one or more required Functions of the Remote Shutdown System are inoperable. This includes any Function listed in Table 3.3.4-1, as well as the control and transfer switches.
The Required Action is to restore the required Function to OPERABLE status within 30 days. The Completion Time is based on operating experience and the low probability of an event that would require evacuation of the control room.
B.1 and B.2 If the Required Action and associated Completion Time of Condition A is not met, the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
(continued)
DIABLO CANYON - UNITS 1 & 2 B 3.0-127 Revision 1
Pressurizer PORVs B 3.4.11 BASES (continued)
ACTIONS Note 1 has been added to clarify that all pressurizer PORVs are treated as separate entities, each with separate Completion Times (i.e., the Completion Time is on a component basis). The exception feo LCO 3.0.4, Note 2, permits entry into MODES 1, 2, and 3 to perform cycling of the PORVs or block valves to verify their OPERABLE status, in the event that teeting was not eatisfactorily performed in lowc MODES A.1 PORVs may be inoperable and capable of being manually cycled, (e.g.,
excessive seat leakage). In this condition, either the PORVs must be restored or the flow path isolated within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The associated block valves is required to be closed but power must be maintained to the associated block valves, since removal of power would render the block valve inoperable. No credit is given for automatic PORV operation in Reference 2 analyses for MODE 1, 2, and 3 transients. As such, the PORVs are considered OPERABLE in either manual control or in the automatic mode. Although a PORV may be designated inoperable, it may be able to be manually opened and closed, and therefore, able to perform its function. PORV isolation may be necessary due to seat leakage, instrumentation problems, automatic control problems, or other causes that do not prevent manual use and do not create a possibility for a small break LOCA. For these reasons, the block valve may be closed but the ACTION requires power be maintained to the valve. This Condition is only intended to permit operation of the plant for a limited period of time not to exceed the next refueling outage (MODE 6) so that maintenance can be performed on the PORVs to eliminate the problem condition. Normally, the PORVs should be available for automatic mitigation of overpressure events and should be returned to OPERABLE and automatic actuation status prior to entering startup (MODE 2).
Quick access to the PORV for pressure control can be made when power remains on the closed block valve. The Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is based on plant operating experience that has shown that minor problems can be corrected or closure accomplished in this time period.
B.1. B.2. and B.3 If one PORV is inoperable and not capable of being manually cycled, it must be either restored or isolated by closing the associated block valve and removing the power to the associated block valve. The Completion Time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> is reasonable, based on challenges to the PORVs during this time period, and provides the operator adequate time to correct the situation.
(continued)
DIABLO CANYON - UNITS I & 2 B 3.4-47 Revision 1
LTOP System B 3.4.12 BASES APPLICABILITY during MODES 1, 2, 3, and MODE 4 above LTOP arming temperature (continued) specified in the PTLR.
Low temperature overpressure prevention is most critical during shutdown when the RCS is water solid, and a mass or heat input transient can cause a very rapid increase in RCS pressure when little or no time is available for operator action to mitigate the event.
ACTIONS A.1 and BA '1 INSERT 5 With one or more SI pumps or two CCPs capable of injecting into the RCS, RCS overpressurization is possible.
To immediately initiate action to restore restricted coolant input capability to the RCS reflects the urgency of removing the RCS from this condition.
C.1, D.1. and D.2 An unisolated accumulator requires isolation within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This is only required when the accumulator pressure is at or more than the maximum RCS pressure for the existing temperature allowed by the P/T limit curves.
If isolation is needed and cannot be accomplished in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, Required ACTION D.1 and Required ACTION D.2 provide two options, either of which must be performed in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. By increasing the RCS temperature to > LTOP arming temperature specified in the PTLR, an accumulator pressure of 600 psig cannot exceed the P/T limits if the accumulators are fully injected. The second option to depressurize the accumulators below the P/T limits from the PTLR also gives this protection.
The Completion Times are based on operating experience that these activities can be accomplished in these time periods and on engineering evaluations indicating that an event requiring LTOP is not likely in the allowed times.
E.1 In MODE 4 when any RCS cold leg temperature is c LTOP arming temperature specified in the PTLR, with one required RCS Class I PORV inoperable, the RCS Class I PORV must be restored to OPERABLE status within a Completion Time of 7 days. Two RCS Class I PORVs are required to provide low temperature overpressure mitigation while withstanding a single failure of an active component.
(continued)
DIABLO CANYON - UNITS 1 & 2 B 3.4-60 Revision 1
Insert 5 A Note prohibits the application of LCO 3.0.4.b to an inoperable LTOP system. There is an increased risk associated with entering MODE 4 from MODE 5 with LTOP inoperable and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.
RCS Leakage Detection Instrumentation B 3.4.15 BASES APPLICABLE SAFETY ANALYSES (continued)
RCS leakage detection instrumentation satisfies Criterion 1 of 10 CFR 50.36(c)(2)(ii).
LCO One method of protecting against large RCS LEAKAGE derives from the ability of instruments to rapidly detect extremely small leaks. This LCO requires instruments of diverse monitoring principles to be OPERABLE to provide a high degree of confidence that extremely small leaks are detected in time to allow actions to place the plant in a safe condition when RCS LEAKAGE indicates possible RCPB degradation.
The LCO is satisfied when monitors of diverse measurement means are available. Thus, the containment sump monitoring systems, the particulate radioactivity monitor and either a CFCU condensate collection monitor or a gaseous radioactivity monitor provides an acceptable minimum.
APPLICABILITY Because of elevated RCS temperature and pressure in MODES 1, 2, 3, and 4, RCS leakage detection instrumentation is required to be OPERABLE. In MODE 5 or 6, the temperature is to be
- 2000F and pressure is maintained low or at atmospheric pressure. Since the temperatures and pressures are far lower than those for MODES 1, 2, 3, and 4, the likelihood of leakage and crack propagation are much smaller. Therefore, the requirements of this LCO are not applicable in MODES 5 and 6.
ACTIONS ACTIONS are mod-iecd by a Note that indicates that the pr-oveisionsf LCO 3.0.4 arc not applicable. As a result, a MODE change is allowed when the required containment sump monitor, the required atmospheric particulate mon.itor, the required atmospheric gaseous monitGr or the required CFCU condensate collection monitor are inoperable. This allowane i6 provided because other instrumentation is available to monitor RCS LEAKAGE.
A.1 and A.2 With the required containment sump monitors inoperable, RCS water inventory balance, the containment atmosphere particulate radioactivity monitor, and the CFCU condensate collection monitoring system will provide indications of changes in leakage. Together with the atmosphere monitors, the periodic surveillance for RCS water inventory balance, SR 3.4.13.1, must be performed at an increased frequency of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to provide information that is adequate to detect leakage. A Note is added allowing that SR 3.4.13.1 is not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after establishing steady state operation as (continued)
DIABLO CANYON - UNITS I & 2 B 3.4-79 Revision 1
RCS Specific Activity B 3.4.16 BASES LCO ensures the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> whole body dose to an individual at the site (continued) boundary during the DBA will be a fraction of the allowed whole body dose.
The SGTR accident analysis (Ref. 2) shows that the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> site boundary dose levels are within acceptable limits. Violation of the LCO may result in reactor coolant radioactivity levels that could, in the event of an SGTR, lead to site boundary doses that exceed the 10 CFR 100 dose guideline limits.
APPLICABILITY In MODES 1 and 2, and in MODE 3 with RCS average temperature 2 5000F, operation within the LCO limits for DOSE EQUIVALENT 1-131 and gross specific activity are necessary to contain the potential consequences of an SGTR to within the acceptable site boundary dose values.
For operation in MODE 3 with RCS average temperature < 5000F, and in MODES 4 and 5, the offsite release of radioactivity from the affected SG in the event of a SGTR is unlikely since the saturation pressure of the reactor coolant is below the lift pressure settings of the main steam safety and relief valves.
ACTIONS A.1 and A.2 A Note to these ACTIONS excludes the MODE change restriction ot
,j[LCO 3.0.4. This exception allows entry into the applicable MODE(S)
INSERT 6 while relying on the ACTIONS even though the ACTIONS may eventually hequire plant shI".dow.
is exreptognallowance is acceptable due to the significant conservatism incorporated into the specific activity limit, the low probability of an event which is limiting due to exceeding this limit, and the ability to restore transient specific activity excursions while the plant remains at, or proceeds to power operation.
With the DOSE EQUIVALENT 1-131 greater than the LCO limit, samples at intervals of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> must be taken to demonstrate that the limits of Figure 3.4.16-1 are not exceeded. The Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is allowed to obtain and analyze a sample. Sampling is continued to provide a trend.
The DOSE EQUIVALENT 1-131 must be restored to within limits within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The Completion Time of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is allowed to permit recovery, if the limit violation resulted from normal iodine spiking.
(continued)
DIABLO CANYON - UNITS 1 & 2 B 3.4-85 Revision 1
Insert 6 A Note permits the use of the provisions of LCO 3.0.4.c. This allowance permits entry into the applicable MODE(S) while relying on the ACTIONS.
ECCS - Shutdown B 3.5.3 BASES LCO (continued)
This LCO is modified by a Note that allows an RHR train to be considered OPERABLE during system alignment and operation for decay heat removal, if capable of being manually realigned (remote or local) to the ECCS mode of operation and not otherwise inoperable.
This allows operation in the RHR mode during MODE 4.
APPLICABILITY In MODES 1, 2, and 3, the OPERABILITY requirements for ECCS are covered by LCO 3.5.2.
In MODE 4 with RCS temperature below 3500F, one OPERABLE ECCS high head and low head train is acceptable without single failure consideration, on the basis of the stable reactivity of the reactor and the limited core cooling requirements.
In MODES 5 and 6, plant conditions are such that the probability of an event requiring ECCS injection is extremely low. Core cooling requirements in MODE 5 are addressed by LCO 3.4.7, "RCS Loops-MODE 5, Loops Filled," and LCO 3.4.8, "RCS Loops-MODE 5, Loops Not Filled." MODE 6 core cooling requirements are addressed by LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation-High Water Level," and LCO 3.9.6, "Residual Heat Removal (RHR) and Coolant Circulation-Low Water Level."
ACTIONS A.1 '
INSERT 7 With no ECCS RHR subsystem OPERABLE, the plant is not prepared to respond to a loss of coolant accident or to continue a cooldown using the RHR pumps and heat exchangers. The Completion Time of immediately to initiate actions that would restore at least one ECCS RHR subsystem to OPERABLE status ensures that prompt action is taken to restore the required cooling capacity. Normally, in MODE 4, reactor decay heat is removed from the RCS by an RHR loop. If no RHR loop is OPERABLE for this function, reactor decay heat must be removed by some alternate method, such as use of the steam generators. The alternate means of heat removal must continue until the inoperable RHR loop components can be restored to operation so that decay heat removal is continuous.
With both RHR pumps and heat exchangers inoperable, it would be unwise to require the plant to go to MODE 5, where the only available heat removal system is the RHR. Therefore, the appropriate action is to initiate measures to restore one ECCS RHR subsystem and to continue the actions until the subsystem is restored to OPERABLE status.
Opening the containment recirculation sump access hatch in MODES I through 4 is considered to be a condition which is outside the accident analysis. Therefore, LCO 3.0.3 must be immediately entered. (Ref. 9)
(continued)
DIABLO CANYON - UNITS I & 2 B 3.5-20 Revision 1
Insert 7 A Note prohibits the application of LCO 3.0.4.b to an inoperable ECCS Centrifugal Charging Pump subsystem when entering MODE 4. There is an increased risk associated with entering MODE 4 from MODE 5 with an inoperable ECCS Centrifugal Charging Pump subsystem and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.
Hydrogen Recombiners B 3.6.8 BASES APPLICABILITY In MODES 5 and 6, the probability and consequences of a LOCA are (continued) low, due to the pressure and temperature limitations in these MODES.
Therefore, hydrogen recombiners are not required in these MODES.
ACTIONS A.1 With one containment hydrogen recombiner inoperable, the inoperable recombiner must be restored to OPERABLE status within 30 days. In this condition, the remaining OPERABLE hydrogen recombiner is adequate to perform the hydrogen control function. However, the overall reliability is reduced because a single failure in the OPERABLE recombiner could result in reduced hydrogen control capability. The 30 day Completion Time is based on the availability of the other hydrogen recombiner, the small probability of a LOCA or SLB occurring (that would generate an amount of hydrogen that exceeds the flammability limit), and the amount of time available after a LOCA or SLB (should one occur) for operator action to prevent hydrogen accumulation from exceeding the flammability limit.
Required Action A. has been modified by a Note that etate& the provisions of LCO 3.0.4 are not applicable. As a result, a MODE change ic allowed when one recombiner is inoperable. This allowance is based on the availability of the other hydrogen recombiner, the small probability of a LOCA or SLB occurring (that would generate an amount of hydrogen that exeeds t Ammaility limit), and the amount of time available after a LOCA or SLB (should one occur) for operator action to prevent hydrogen a-cumUlation from exceeding the flammability limit.
B.1 and B.2 With two hydrogen recombiners inoperable, the ability to perform the hydrogen control function via alternate capabilities must be verified by administrative means within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The alternate hydrogen control capabilities are provided by the containment Hydrogen Purge System.
The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time allows a reasonable period of time to verify that a loss of hydrogen control function does not exist. In addition, the alternate hydrogen control system capability must be verified once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter to ensure its continued availability.
Both the initial verification and all subsequent verifications may be performed as an administrative check by examining logs or other information to determine the availability of the key locked alternate hydrogen control system. It does not mean to perform the Surveillances are needed to demonstrate OPERABILITY of the alternate hydrogen control system. If the ability to perform the (continued)
DIABLO CANYON - UNITS 1 & 2 B 3.6-49 Revision 1
ADVs B 3.7.4 BASES (continued)
APPLICABILITY In MODES 1, 2, and 3, all four ADVs are required to be OPERABLE. In MODE 4, only the ADVs associated with the steam generators being relied upon for heat removal, are required to be OPERABLE.
In MODE 5 or 6, an SGTR is not a credible event.
ACTIONS A.l With one required ADV line inoperable, action must be taken to restore OPERABLE status within 7 days. The 7 day Completion Time allows for the redundant capability afforded by the remaining OPERABLE ADV lines, a non-safety grade backup in the Steam Bypass System, and MSSVs and is based on a PRA analysis and the low probability of a SGTR and LOOP event occurring during this period that would require the ADV lines. Required Action A.! is modified by a Note indicating that LCOQ 3.0.4 does not apply.
B.1 With two ADV lines inoperable, action must be taken to restore at least one ADV line to OPERABLE status. This will result in at least three operable ADVs. Since the block valve can be closed to isolate an ADV, some repairs may be possible with the unit at power. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable to repair inoperable ADV lines, based on the availability of the Steam Dump System (40% steam dump valves to the condenser) and MSSVs, and the low probability of an event occurring during this period that would require the ADV lines.
C.1 With three or more ADV lines inoperable, action must be taken to restore at least two ADV lines to OPERABLE status. This will result in at least two operable ADVs. Since the block valve can be closed to isolate an ADV, some repairs may be possible with the unit at power.
The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion Time is reasonable to repair inoperable ADV lines, based on the availability of the Steam Dump System (40% steam dump valves to the condenser) and MSSVs, and the low probability of an event occurring during this period that would require the ADV lines.
D.I and D.2 If the ADV lines cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4, without reliance upon steam generator for heat removal, within 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
(continued)
DIABLO CANYON - UNITS I & 2 B 3.7-21 Revision 1
AFW System B. 3.7.5 BASES LCO (continued) each powered by a separated vital bus, be OPERABLE in two diverse paths, each supplying AFW to separate steam generators. The turbine driven AFW pump is required to be OPERABLE with redundant steam supplies from each of two main steam lines upstream of the MSIVs, and shall be capable of supplying AFW to any of the steam generators.
The piping, valves, instrumentation, and controls in the required flow paths also are required to be OPERABLE.
The operability of the AFW suction flow path is assured by verifying the condensate storage tank outlet valve open and by verifying the capability to align the fire water storage tank to the AFW pump suction.
The LCO is modified by a Note indicating that one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4. This is because of the reduced heat removal requirements and short period of time in MODE 4 during which the AFW is required and the insufficient steam available in MODE 4 to power the turbine driven AFW pump.
APPLICABILITY In MODES 1, 2, and 3, the AFW System is required to be OPERABLE in the event that it is called upon to function when the MFW is lost. In addition, the AFW System is required to supply enough makeup water to replace the steam generator secondary inventory, lost as the unit cools to MODE 4 conditions.
In MODE 4 the AFW System may be used for heat removal via the steam generators.
In MODE 5 or 6, the steam generators are not normally used for heat removal, and the AFW System is not required.
ACTIONS A.1
-- INSERT 8 If one of the two steam supplies to the turbine driven AFW train is inoperable, action must be taken to restore OPERABLE status within 7 days. The 7 day Completion Time is reasonable, based on the following reasons:
- a.
The redundant OPERABLE steam supply to the turbine driven AFW pump;
- b.
The availability of redundant OPERABLE motor driven AFW pumps; and
- c.
The low probability of an event occurring that requires the inoperable steam supply to the turbine driven AFW pump.
(continued)
DIABLO CANYON - UNITS 1 & 2 B 3.7-26 Revision 1
Insert 8 A Note prohibits the application of LCO 3.0.4.b to an inoperable AFW train. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an AFW train inoperable and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.
AC Sources - Operating B 3.8.1 BASES APPLICABILITY The AC sources are required to be OPERABLE in MODES 1, 2, 3, and 4 to ensure that:
- a.
Acceptable fuel design, limits and reactor coolant pressure boundary limits are not exceeded as a result of AQOs or abnormal transients; and
- b.
Adequate core cooling is provided and containment OPERABILITY and other vital functions are maintained in the event of a postulated DBA.
The AC power requirements for MODES 5 and 6 are covered in LCO 3.8.2, "AC Sources - Shutdown."
ACTIONS A.1 V INSERT 9 To ensure a highly reliable power source remains with one offsite circuit inoperable, it is necessary to verify the OPERABILITY of the remaining required offsite circuit on a more frequent basis. Since the Required Action only specifies "perform," a failure of SR 3.8.1.1 acceptance criteria does not result in a Required Action not met. However, if a second required circuit fails SR 3.8.1.1, the second offsite circuit is inoperable, and Condition C, for two offsite circuits inoperable, is entered.
The 230 kV system should be considered inoperable when the DCPP Shift Supervisor has been notified of system inoperability by the Diablo Canyon Switching Center, Grid Operations Scheduling, or Grid Shift Supervisor, in accordance with Transmission Operating Procedure 0-23, "Operating Instructions for Reliable Transmission Service for Diablo Canyon P.P."
A.2 According to Regulatory Guide 1.93 (Ref. 6), operation may continue in Condition A for a period that should not exceed 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. With one offsite circuit inoperable, the reliability of the offsite system is degraded, and the potential for a loss of offsite power is increased, with attendant potential for a challenge to the unit safety systems. In this Condition, however, the remaining OPERABLE offsite circuit and DGs are adequate to supply electrical power to the onsite Class 1 E Distribution System.
The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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.
(continued)
DIABLO CANYON - UNITS 1 & 2 B 3.8-5 Revision 1
Insert 9 A Note prohibits the application of LCO 3.0.4.b to an inoperable DG. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable DG and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.
Boron Concentration B 3.9.1 BASES (continued)
APPLICABLE SAFETY ANALYSIS During refueling operations, the reactivity condition of the core is consistent with the initial conditions assumed for the boron dilution accident in the accident analysis and is conservative for MODE 6. The boron concentration limit specified in the COLR is based on the core reactivity at the beginning of each fuel cycle (the end of refueling) and includes an uncertainty allowance.
The required boron concentration and the plant refueling procedures that verify the correct fuel loading plan (including core mapping) ensure that the kf of the core will remain < 0.95 during the refueling operation.
Hence, at least a 5% Ak/k margin of safety is established during refueling.
During refueling, the water volume in the spent fuel pool, the transfer canal, the refueling canal, the refueling cavity, and the reactor vessel form a single mass. As a result, the soluble boron concentration is relatively the same in each of these volumes.
The limiting boron dilution accident analyzed occurs in MODE 5 (Ref. 2). It is based upon a maximum dilution flow of 300 g.p.m. and prompt identification and operation preclude the event from proceeding to a boron dilution accident. Prompt identification is assured through audible count rate instrumentation, visual count rate instrumentation and a high source range flux level alarm.
The RCS boron concentration satisfies Criterion 2 of 1 OCFR50.36(c)(2)(ii).
LCO The LCO requires that a minimum boron concentration be maintained in the filled portions of the RCS, the refueling canal, and the refueling cavity that have direct access to the reactor vessel while in MODE 6.
The boron concentration limit specified in the COLR ensures that a core k.f of
- 0.95 is maintained during fuel handling operations.
Violation of the LCO could lead to an inadvertent criticality during MODE 6.
APPLICABILITY This LCO is applicable in MODE 6 to ensure that the fuel in the reactor vessel will remain subcritical. The required boron concentration ensures a kff < 0.95. Above MODE 6, LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," LCO 3.1.5, "Shutdown Bank Insertion Limits," and LCO 3.1.6, "Control Bank Insertion Limits," ensures that an adequate amount of negative reactivity is available to shut down the reactor and maintain it subcritical. A Note is added to the applicability to assure that MODE 6 cannot be entered unless boron concentration limits are met.
DIABLO CANYON - UNITS 1 & 2 B, 3.9-1 Revision 1
RHR and Coolant Circulation - Low Water Level B 3.9.6 BASES LCO (continued)
An OPERABLE RHR loop consists of an RHR pump, a heat exchanger, valves, piping, instruments and controls to ensure an OPERABLE flow path and to determine the low end temperature. The flow path starts in one of the RCS hot legs and is returned to the RCS cold legs. An operable RHR loop must be capable of being realigned to provide an operable flow path.
APPLICABILITY Two RHR loops are required to be OPERABLE, and one RHR loop must be in operation in MODE 6, with the water level < 23 ft above the top of the reactor vessel flange, to provide decay heat removal.
Requirements for the RHR System in other MODES are covered by LCOs in Section 3.4, Reactor Coolant System (RCS), and Section 3.5, Emergency Core Cooling Systems (ECCS). RHR loop requirements in MODE 6 with the water level 2 23 ft are located in LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation-High Water Level." A Note Os added to the applicability to aseur-e that MODE 6 operation with water level - 23 ft. is not permitted unless two RHR loops are operable.
ACTIONS A.1 and A.2 If less than the required number of RHR loops are OPERABLE, action shall be immediately initiated and continued until the RHR loop is restored to OPERABLE status and to operation or until 2 23 ft of water level is established above the reactor vessel flange. When the water level is Ž 23 ft above the reactor vessel flange, the Applicability changes to that of LCO 3.9.5, and only one RHR loop is required to be OPERABLE and in operation. An immediate Completion Time is necessary for an operator to initiate corrective actions.
B. 1 If no RHR loop is in operation, there will be no forced circulation to provide mixing to establish uniform boron concentrations. The suspension of any operation involving a reduction in Reactor Coolant Boron Concentration will reduce the likelihood of boron stratifcation in the RCS.
B.2 If no RHR loop is in operation, actions shall be initiated immediately, and continued, to restore one RHR loop to operation. Since the unit is in Conditions A and B concurrently, the restoration of two OPERABLE RHR loops and one operating RHR loop should be accomplished expeditiously.
DIABLO CANYON - UNITS 1 & 2 B 3.9-20 Revision 1