ML032040047
| ML032040047 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire  |
| Issue date: | 07/14/2003 |
| From: | Mccollum W Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML032040047 (21) | |
Text
Duke a Duke Duke Energy Corporation
~~~~~~~~~~~~~~~~~~~~~~526 South Church Street Energy. P.O. Box 1006 Charlotte, NC 28201-1006 July 14, 2003 U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk
SUBJECT:
Duke Energy Corporation McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369, 50-370 Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413, 50-414 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, "Accumulators,ff Using the Consolidated Line Item Improvement Process In accordance with the provisions of 10CFR50.90, Duke Energy Corporation (Duke) proposes a revision to the McGuire and Catawba Nuclear Station Facility Operating Licenses and Technical Specifications (TS) and Bases. The proposed amendment would extend the completion time from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Condition B of Technical Specification (TS) 3.5.1, "Accumulators." The change is consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-370, "Risk Informed Evaluation of an Extension to Accumulator Completion Times for Westinghouse Plants." The availability of this technical specification improvement was announced in the Federal Register on March 12, 2003 as part of the consolidated line item improvement process (CLIIP).
The contents of this amendment package are as follows: provides a description of the proposed change and confirmation of applicability. Attachment 2A provides
]1C
U.S. Nuclear Regulatory Commission Page 2 July 14, 2003 marked copies of the affected TS and Bases pages for McGuire showing the proposed changes. Attachment 2B provides marked copies of the affected TS and Bases pages for Catawba showing the proposed changes. Attachment 3A, containing reprinted pages of the affected TS and Bases pages for McGuire, will be provided to the NRC upon issuance of the approved amendment. Attachment 3B, containing reprinted pages of the affected TS and Bases pages for Catawba, will be provided to the NRC upon issuance of the approved amendment. There are no new regulatory commitments associated with this proposed change.
Since the proposed license amendment is a CLIIP item, Duke requests approval by October 17, 2003, with the amendment being implemented within 30 days of the receipt of NRC approval.
In accordance with Duke administrative procedures and the Quality Assurance Program Topical Report, the site-specific changes contained in this LAR have been reviewed and approved by the respective McGuire and Catawba Plant Operations Review Committee. This LAR has also been reviewed and approved on an overall basis by the Duke Corporate Nuclear Safety Review Board. Pursuant to 10CFR50.91, a copy of this LAR is being sent to the State of North Carolina and the State of South Carolina.
Inquiries on this matter should be directed to J. A.
Effinger at (704) 382-8688.
Very truly yours, W.R. Mc CollumJr Senior Vice Presi $nt Nuclear Support
U.S. Nuclear Regulatory Commission Page 3 July 14, 2003 W. R. Mc Collum, Jr., being duly sworn, affirms that he is the person who subscribed his name to the foregoing statement, and that all matters and facts set forth herein are true and correct to the best of his knowledge.
W. R. Mc Collum, Jr.,
Subscribed and sworn to me:
0Dat'e )~p Notary Public My co-mmission expires: %*-d 22, /206 SEAL
U.S. Nuclear Regulatory Commission Page 4 July 14, 2003 xc (w/attachments):
L. A. Reyes U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 R. E. Martin NRC Project Manager (MNS) (CNS)
U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 J. B. Brady Senior Resident Inspector (MNS)
U. S. Nuclear Regulatory Commission McGuire Nuclear Site E. F. Guthrie Senior Resident Inspector (CNS)
U. S. Nuclear Regulatory Commission Catawba Nuclear Site B. 0. Hall, Section Chief Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 H. J. Porter, Director Division of Radioactive Waste Management Bureau of Land and Waste Management Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201
U.S. Nuclear Regulatory Commission Page 5 July 14, 2003 bxc wlattachments:
C. J. Thomas G. D. Gilbert M. T. Cash K. E. Nicholson J. M. Ferguson (RGC data file)
K. L. Crane Catawba Owners: NCMPA-1, SREC, PMPA, NCEMC McGuire Master File (MGOlDM)
Catawba Document Control File 801.01 (CN04DM)
ELL
ATTACHMENT 1 DESCRIPTION OF THE PROPOSED CHANGE AND CONFIRMATION OF APPLICABILITY
DESCRIPTION AND ASSESSMENT
1.0 DESCRIPTION
The proposed License amendment extends the completion time from 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Condition B of Technical Specification (TS) 3.5.1, "Accumulators."
The changes are consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-370, "Risk Informed Evaluation of an Extension to Accumulator Completion Times for Westinghouse Plants." The availability of this technical specification improvement was announced in the Federal Register on March 12, 2003 as part of the consolidated line item improvement process (CLIIP).
2.0 ASSESSMENT -
2.1 Applicability of Published Safety Evaluation Duke has reviewed the safety evaluation published on July 15, 2002 (67 FR 46542) as part of the CLIIP. This verification included a review of the NRC staff's evaluation as well as the supporting information provided to support TSTF-370 (i.e., WCAP-15049-A, "Risk-Informed Evaluation of an Extension to Accumulator Completion Times') dated May 18, 1999. Duke has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to the McGuire and Catawba Nuclear Stations, Units 1 and 2, and justify this amendment for the incorporation of the changes to the McGuire and Catawba Nuclear Station Technical Specifications.
2.2 Optional Changes and Variations Duke is not proposing any variations or deviations from the technical specification changes described in TSTF-370 or the NRC staff's model safety evaluation published on July 15, 2002.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Determination Duke has reviewed the proposed no significant hazards consideration determination published on July 15, 2002 (67 FR 46542) as part of the CLIIP. Duke has concluded that the proposed determination presented in the notice is applicable to the McGuire and Catawba Nuclear Stations and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
3.2 Verification and Commitments There are no new regulatory commitments associated with this proposed change.
4.0 ENVIRONMENTAL EVALUATION Duke has reviewed the environmental evaluation included in the model safety evaluation published on July 15, 2002 (67 FR 46542) as part of the CLIIP. Duke has concluded that the NRC staff's findings presented in that evaluation are applicable to the McGuire and Catawba Nuclear Stations and the evaluation is hereby incorporated by reference for this application.
ATTACHMENT 2A McGUIRE UNITS 1 AND 2 TECHNICAL SPECIFICATIONS AND TECHNICAL SPECIFICATION BASES MARKED COPY
Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 Four ECCS accumulators shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS pressure > 1000 psig.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable due to boron concentration to within concentration not within limits.
limits.
B. One accumulator B.1 Restore accumulator to (,ours inoperable for reasons OPERABLE status.
other than Condition A. 7 J 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 of Condition A or B AND not met.
C.2 Reduce RCS pressure to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
< 1000 psig.
D. Two or more D.1 Enter LCO 3.0.3. Immediately accumulators inoperable.
McGuire Units 1 and 2 3.5.1 -1 Amendment Nos.,
Accumulators B 3.5.1 BASES APPLICABILITY In MODES 1 and 2, and in MODE 3 with RCS pressure > 1000 psig, the accumulator OPERABILITY requirements are based on full power operation. Although cooling requirements decrease as power decreases, the accumulators are still required to provide core cooling as long as elevated RCS pressures and temperatures exist.
This LCO is only applicable at pressures > 1000 psig. At pressures
< 1000 psig, the rate of RCS blowdown is such that the ECCS pumps can provide adequate injection to ensure that peak clad temperature remains below the 10 CFR 50.46 (Ref. 3) limit of 22001F for small break LOCAs and there is a high level of probability that the peak cladding temperature does not exceed 22000°F for large break LOCAs.
In MODE 3, with RCS pressure < 1000 psig, and in MODES 4, 5, and 6, the accumulator motor operated isolation valves are closed to isolate the accumulators from the RCS. This allows RCS cooldown and depressurization without discharging the accumulators into the RCS or requiring depressurization of the accumulators.
ACTIONS A.1 If the boron concentration of one accumulator is not within limits, it must be returned to within the limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In this Condition, ability to maintain subcriticality or minimum boron precipitation time may be reduced. The boron in the accumulators contributes to the assumption that the combined ECCS water in the partially recovered core during the early reflooding phase of a large break LOCA is sufficient to keep that portion of the core subcritical. One accumulator below the minimum boron concentration limit, however, will have no effect on available ECCS water and an insignificant effect on core subcriticality during reflood.
Boiling of ECCS water in the core during reflood concentrates boron in the saturated liquid that remains in the core. In addition, current analysis techniques demonstrate that the accumulators do not discharge following a large main steam line break for the plant. Even if they do discharge, their impact is minor and not a design limiting event. Thus, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed to return the boron concentration to within limits.
B.1 If one accumulator is inoperable for a reason other than boron
_--c~ont ntration, the accumulator must be returned to OPERABLE status tZ withi Whoug In this Condition, the required contents of three accumulators cannot be assumed to reach the core during a LOCA. Due to the severity of the consequences should a LOCA occur in these McGuire Units 1 and 2 B 3.5.1-5 Revision No.,' R'
Accumulators B 3.5.1 BASES ACTIONS (continued) conditions, theohour Completion Time to open the valve, remove power to the valve, or restore the proper water volume or nitrogen cover pressure ensures that prompt action will be taken to return the inoperable accumulator to OPERABLE status. The Completion Time minimizes the potential for exposure of the plant to a LOCA under these conditions 4 ~~~C.1 andC2 --
If the accumulator cannot be returned to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and RCS pressure reduced to
- 1000 psig 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 plant conditions from full power conditions in an orderly manner and without challenging plant systems.
D.1 If more than one accumulator is inoperable, the plant is in a condition outside the accident analyses; therefore, LCO 3.0.3 must be entered immediately.
SURVEILLANCE SR 3.5.1.1 REQUIREMENTS Each accumulator valve should be verified to be fully open every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. This verification ensures that the accumulators are available for injection and ensures timely discovery if a valve should be less than fully open. If an isolation valve is not fully open, the rate of injection to the RCS would be reduced. Although a motor operated valve position should not change with power removed, a closed valve could result in not meeting accident analyses assumptions. This Frequency is considered reasonable in view of other administrative controls that ensure a mispositioned isolation valve is unlikely.
SR 3.5.1.2 and SR 3.5.1.3 Every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, borated water volume and nitrogen cover pressure are verified for each accumulator. This is typically performed using the installed control room indication. This Frequency is sufficient to ensure adequate injection during a LOCA. Because of the static design of the accumulator, a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Frequency usually allows the operator to identify McGuire Units 1 and 2 B 3.5.1-6 Revision No. X
Accumulators B 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued) changes before limits are reached. Operating experience has shown this Frequency to be appropriate for early detection and correction of off normal trends.
SR 3.5.1.4 The boron concentration should be verified to be within required limits for each accumulator every 31 days since the static design of the accumulators limits the ways in which the concentration can be changed.
The 31 day Frequency is adequate to identify changes that could occur from mechanisms such as stratification or inleakage. Sampling the affected accumulator within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a 1% tank volume increase will identify whether inleakage has caused a reduction in boron concentration to below the required limit. It is not necessary to verify boron concentration if the added water inventory is from the refueling water storage tank (RWST), because the water contained in the RWST is within the accumulator boron concentration requirements. This is consistent with the recommendation of NUREG-1366 (Ref-.
SR 3.5.1.5 Verification every 31 days that poujr is removed from each accumulator isolation valve operator (see Ref. when the RCS pressure is > 1000 psig ensures that an active failure could not result in the undetected closure of an accumulator motor operated isolation valve. If this were to occur, only two accumulators would be available for injection given a single failure coincident with a LOCA. Since power is removed under administrative control, the 31 day Frequency will provide adequate assurance that power is removed.
This SR allows power to be supplied to the motor operated isolation valves when RCS pressure is
- 1000 psig, thus allowing operational flexibility by avoiding unnecessary delays to manipulate the breakers during plant startups or shutdowns. Even with power supplied to the valves, inadvertent closure is prevented by the RCS pressure interlock associated with the valves.
Should closure of a valve occur in spite of the interlock, the Si signal provided to the valves would open a closed valve in the event of a LOCA.
McGuire Units 1 and 2 B 3.5.1 -7 Revision No.,W
Accumulators B 3.5.1 BASES REFERENCES 1. IEEE Standard 279-1971.
- 2. UFSAR, Chapter 6.
- 3. 10 CFR 50.46.
- 4. DPC-NE-3004.
- 5. 10 CFR 50.36, Technical Specification, (c)(2)(ii).
Xj NUREG-1366, February 1990.
{ A)/. Duke letter to NRC, "Cold Leg Accumulator Isolation Valves", dated September 8, 1987 v.W4AP-1)OTA0J19AJ-e4- 99 McGuire Units 1 and 2 B 3.5.1 -8 'Aw Revision No. -WN
ATTACHMENT 2B CATAWBA UNITS 1 AND 2 TECHNICAL SPECIFICATIONS AND TECHNICAL SPECIFICATION BASES MARKED COPY
Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 Accumulators LCO 3.5.1 Four ECCS accumulators shall be OPERABLE.
APPLICABILITY: MODES 1 and 2, MODE 3 with RCS pressure > 1000 psig.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable due to boron concentration to within concentration not within limits.
limits.
B. One accumulator B.1 Restore accumulator to fhours inoperable for reasons OPERABLE status.
other than Condition A. Cv 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 of Condition A or B AND not met.
C.2 Reduce RCS pressure to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
< 1000 psig.
D. Two or more D.1 Enter LCO 3.0.3. Immediately accumulators inoperable.
Catawba Units 1 and 2 3.5.1 -1 Amendment Nos. Tzat5-
Accumulators B 3.5.1 BASES APPLICABILITY (continued)
This LCO iis only applicable at pressures > 1000 psig. At pressures
<lOOOpsi g, the rate of RCS blowdown is such that the ECCS pumps can provide ad1equate injection to ensure that peak clad temperature remains below the 10 CFR 50.46 (Ref. 3) limit of 22000F for small break LOCAs and there is a high level of probability that the peak cladding temperature te tv ~~~~does not eexceed 22000 F for large break LOCAs.
In MODE, 3, with RCS pressure *1000 psig, and in MODES 4, 5, and 6, 0 1) \the accum ulator motor operated isolation valves are dosed to isolate the accumulators from the RCS. This allows RCS cooldown and depressur ization without discharging the accumulators into the RCS or requiring cdepressurization of the accumulators.
i1 X ACTIONS A.1 FE h g l If the boro in concentration of one accumulator is not within limits, it must be returne d to within the limits within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. In this Condition, ability to tL ~~~~~maintain s;ubcriticality or minimum boron precipitation time may be reduced. The boron in the accumulators contributes to the assumption uL 6 wthat the cc)mbined ECCS water in the partially recovered core during the iL _early reflowoding phase of a large break LOCA is sufficient to keep that 8 ,, s portion ofthe core subcritical. One accumulator below the minimum 2Qt~
o 1boron con centration limit, however, will have no effect on available ECCS Ji > I water and an insignificant effect on core subcriticality during reflood.
At .0 , Boiling of ECCS water in the core during reflood concentrates boron in qF satura,ted liquid that remains in the core. In addition, current analysis
~~~~~~the technique s demonstrate that the accumulators do not discharge following a large m. ain steam line break for the plant. Even if they do discharge, q In their impa ct is minor and not a design limiting event. Thus, 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is J _ allowed toDreturn the boron concentration to within limits.
vL
<B.1 If one acc:umulator is inoperable for a reason other than boron
~~~~~ ~~~concmitra tion, the accumulator must be returned to OPERABLE status oui6.In this Condition, the required contents of three accumula tors cannot be assumed to reach the core during a LOCA. Due to the sev Verity of the consequences should a LOCA occur in these
- , th~.our Completion lime to open the valve, remove power to the vah ve, or restore the proper water volume or nitrogen cover pressure ensures that prompt action will be taken to return the inoperable
\ ~~~~~accumula' tor to OPERABLE status. The Completion Time minimizes the
\ ~~~~~~potential ifor exposure of the plant to a LOCA under these conditions.A I
Catawba Units 1 and 2 B 3.5.1-5 Revision NoX
Accumulators B 3.5.1 BASES SURVEILLANCE REQUIREMENTS (continued)
SR 3.5.1.4 The boron concentration should be verified to be within required limits for each accumulator every 31 days since the static design of the accumulators limits the ways in which the concentration can be changed.
The 31 day Frequency is adequate to identify changes that could occur from mechanisms such as stratification or inleakage. Sampling the affected accumulator within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after a 75 gallon increase will identify whether inleakage has caused a reduction in boron concentration to below the required limit. It is not necessary to verify boron concentration if the added water inventory is from the refueling water storage tank (RWST), because the water contained in the RWST is within the accumulator boron concentration requirements. This is consistent with the recommendation of NUREG-1366 (Ref.,6).
SR 3.5.1.5 Verification every 31 days that power is removed from each accumulator isolation valve operators for N154A, N165B, N176A, and N188B when the RCS pressure is > 1000 psig ensures that an active failure could not result in the undetected closure of an accumulator motor operated isolation valve. If this were to occur, only two accumulators would be available for injection given a single failure coincident with a LOCA.
Since power is removed and circuit breakers padlocked under administrative control, the 31 day Frequency will provide adequate assurance that power is removed.
This SR allows power to be supplied to the motor operated isolation valves when RCS pressure is < 1000 psig, thus allowing operational flexibility by avoiding unnecessary delays to manipulate the breakers during plant startups or shutdowns. Even with power supplied to the valves, inadvertent closure is prevented by the RCS pressure interlock associated with the valves.
Should closure of a valve occur in spite of the interlock, the Si signal provided to the valves would open a closed valve in the event of a LOCA.
Catawba Units 1 and 2 B 3.5.1-7 Revision No. k
Accumulators B 3.5.1 BASES REFERENCES 1. IEEE Standard 279-1971.
- 2. UFSAR, Chapter 6.
- 3. 10 CFR 50.46.
- 4. DPC-NE-3004.
- 5. 10 CFR 50.36, Technical Specification, (c)(2)(ii).
NUREG-1366, February 1990.
Catawba Units 1 and 2 B 3.5.1-8 Revision No.x
ATTACHMENT 3A McGUIRE UNITS 1 AND 2 TECHNICAL SPECIFICATIONS AND TECHNICAL SPECIFICATION BASES (TO BE PROVIDED TO THE NRC UPON ISSUANCE OF APPROVED AMENDMENT)
ATTACHMENT 3B CATAWBA UNITS 1 AND 2 TECHNICAL SPECIFICATIONS AND TECHNICAL SPECIFICATION BASES (TO BE PROVIDED TO THE NRC UPON ISSUANCE OF APPROVED AMENDMENT)