ML20211J986
| ML20211J986 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/01/1999 |
| From: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20211J990 | List: |
| References | |
| NUDOCS 9909070082 | |
| Download: ML20211J986 (14) | |
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- Charles H. Cruse Calvert Chffs Nuclear Power Plant Vice President - 1650 Calvert Chtfs Parkway Nuclear Energy Lusby, Maryland 20657 410 4954455 e ,,
A Member of the Constellation Energy Group September 1,1999 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk
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SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318
- License Amendment Request: Minor Changes to Technical Specifications Pursuant to 10 CFR 50.90, the Baltimore Gas and Electric Company hereby requests an amendment to Operating Licenses Number DPR-53 and DPR-69 to:
- 1. Change the definition of Azimuthal Power Tilt in Technical Specification 1.1;
- 2. Correct the peak linear heat rate safety limit in Technical Specification 2.1.1.2;
- 3. Correct the DC voltage range listed in Surveillance Requirements 3.8.1.9 and 3.8.1.15;
- 4. Correct the loss of voltage and degraded voltage settings in Surveillance Requirement 3.3.6.2;
- 5. Correct the list of core operating limits in Technical Specification 5.6.5.a;
- 6. Correct a note on Technical Specification Figure 2.1.1-1;
- 7. Remove references to Unit 2, Cycle 12 in various Technical Specifications; and
- 8. Correct a typographical error in Technical Specification 5.6.
The proposed changes are shown in Attachment (3). The final Technical Specification pages will be renumbered if necessary to accommodate the insertion of these changes.
We have considered the possibility of significant hazards associated with these changes and have determined there are none (see Attachments I and 2 for a complete discussion). We have also determined that operation with the proposed changes would not result in any significant change in the i types or amounts of any effluents that may be released offsite, nor would it result in any significant j increase in individual or cumulative occupational radiation exposure. Therefore, the proposed amendment is eligible for categorical exclusion as set forth in 10 CFR St.22(c)(9). Pursuant to 10 CFR St.22(b), no environmental impact statement or environmental assessment is needed in connection with the proposed amendment.
These proposed changes to the Technical Specifications and our determination of significant hazards have been approved by our Plant Operations and Safety Review Committee and Offsite Safety Review Committee, and they have concluded that implementation of these changes will not result in an undue risk to the health and safety of the public.
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- i. m .. 4n j j 9909070082 990901 h5 yDR ADOCK 05000317 PDR I}'
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. ,4 l Docum:nt Control Desk-
. September 1,1999 u Page 2
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This change is requested to be approved by November 1999.
Should you have any questions regarding this matter, we will be pleased to discuss them with you.
' Very traly yours,
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f STATE OF MARYLAND :
- TO WIT:
~ COUNTY OF CALVERT :
1, Charles H. Cruse, being duly sworn, state that I am Vice President, Nuclear Energy Division, B'altimore Gas and Electric Company (BGE), and that I am duly authorized to execute and file this License -
Amendment Request on behalf of BGE. To the best of my knowledge and belief, the statements contained in this document are true and correct. To the extent that these statements are not based on my personal knowledge, they are based upon information provided by other BGE employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable. '
Iw+ff Aw Subs ibed and sworn before me, a Notary Public in and for the State of Maryland and County of
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.this /aLdayof h2hl#AJ999.
I WITNESS my Hand and Notarial Seal: fAtt A f ) 2 A Notary Public My Commission Expires: b '
I MN1 Date CilC/EMT/bjd Attachments: (1) . Background and Analysis (2)- Determination of Significant Hazards (3) Proposed Changes to Technical Specifications cc: R. S. Fleishman, Esquire H. J. Miller, NRC j- ' J. E. Silberg, Esquire Resident inspector,NRC i S. S. Bajwa, NRC R.1. McLean, DNR A. W. Dromerick, NRC J. H. Walter, PSC l
ATTACHMENT (1) l I
BACKGROUND AND ANALYSIS '
Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant September 1,1999
ATTACHMENT (1)
- BACKGROUND AND ANALYSIS ,
BACKGROUND Change the Definition of Azimuthal Power Tilt in their Infobulletin 97-07, Revision 1, (December 31, 1997) Asea Brown .Boveri, Inc.-Combustion Engineering, Inc. (ABB-CE) stated they had found a discrepancy in the Technical Specification definition of azimuthal power tilt. This discrepancy was found to exist in all CE Nuclear Steam Supply System analog plants that use CECOR for monitoring and surveillance, and that use ABB-CE safety analysis methodology. Calvert Cliffs is one of those plants. The new definition yields a slightly more conservative value when calculating azimuthal power tilt. Baltimore Gas and Electric Company was already using the definition in the infobulletin when the infobulletin was issued and, therefore, has not operated the plant in a non-conservative manner.
- The proposed definition is, " Azimuthal Power Tilt shall be the power asymmetry between azimuthally symmetric core locations."
Correct the Peak Linear Heat Rate Safety Limit Technical Specification 2.1.1.2 states that the peak linear heat rate safety limit shall be maintained s 21 kW/R. This number is in error.
. The peak linear heat rate safety limit was changed from s 21 kW/ft to s 22 kW/ft in License Amendment Nos. 88 (Unit 1) and 61 (Unit 2). This number was valid for both units at the time ofimplementation of
- the improved Standard Technical Specifications (ITS). When the ITS were written, a value of peak linear heat rate safety limit s 21 kW/ft was inadvertently entered.
The operational limit of the peak linear heat rate is 14.3 kW/R (Technical Specification 3.2.1 and Core Operating Limits report figure 3.2.1- 1). Changing the safety limit does not change the operational limit; therefore, the plant has not been operated in a non-conservative manner.
Correct the Diesel Generator loss of Voltage and Degraded Voltage Settings Technical Specification Surveillance Requirement (SR) 3.3.6.2 gives a degraded voltage function and a loss-of-voltage function for diesel generators. This is incomplete information.
- In License Amendment Nos. 226 (Unit 1) and 200 (Unit 2), degraded voltage was divided into transient degraded voltage and steady-state degraded voltage. The license amendment request that proposed these amendments included pages for both the then-current Technical Specifications and the ITS. The pages for the Technical Specifications current at the time were properly marked up in the license amendment request, but the ITS page that included the transient degraded voltage and steady-state degraded voltage changes was inadvertently omitted from the license amendment request. Consequently, the entries for transient degraded voltage and steady-state degraded voltage are not in SR 3.3.6.2 of the Technical Specifications currently in use.
We recognized the error in the issuance ofITS and have conducted surveillances for transient and steady-state degraded voltage since the approval of License Amendment Nos. 226 and 200.
Correct the Diesel Generator Voltage Range Technical Specification SRs 3.8.1.9 and 3.8.1.15 require each diesel to be started from a stand-by condition. Surveillance Requirement 3.8.1.9 requires that the generator reach 2 3740 volts within 1
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, ,o ATTACHMENT (1)
BACKGROUND AND ANALYSIS 1
10 seconds.. After steady-state conditions are reached, both SRs require the generator to maintain a voltage range of > 3740 volts and s 4580 volts. These voltage ranges are in error.
The Baltimore Gas and Electric Company ITS conversion added voltage requirements to SRs 3.8.1.9 and 3.8.1.15 consistent with SR 3.8.1.3. License Amendments Nos.226 and 200 changed the voltage requirement for SR 3.8.1.3 to 24060 volts and s 4400 volts. The voltage range currently in SRs 3.8.1.9 and 3.8.1.15 is the value of the range before License Amendment Nos.226 and 200. It was incorrectly left in SRs 3.8.1.9 and 3.8.1.15 when the Technical Specifications were changed to ITS.
The error was recognized before the surveillance was performed. The procedures controlling the conduct of the surveillance were changed to use the correct values.
Correct the List of Core Operating Limits Technical Specification 5.6.5.a lists limits that are to be included in the Core Operating Limits Report. In the transition to the ITS, Technical Specifications 3.1.4 (Control Element Assembly Alignment) and 3.3.1 (Reactor Protective System - Operating) were inadvertently omitted from the list.
Correct Figure 2.1.1-1 A note on Technical Specification Figure 2.1.1-1 was changed in License Amendment Nos. 227 (Unit 1) and 201 (Unit 2) (ITS) to delete reference to Figure B2.1-1. Figure B2.1-1 was deleted from the Technical Specification Bases in the transition to ITS. In License Amendment Nos. 228 (Unit 1) and 202 (Unit 2), an old version of Figure 2.1.1-1 was used, and the reference to Figure B2.1-1 was thus inadvertently put back in the note.
The proposed correction will replace the reference to Figure B2.1-1 with the wording approved in License Amendment Nos. 227 and 201.
Remove References to Unit 2, Cycle 12 License Amendment Nos. 228 and 202 added notes to indicate areas in the Technical Specifications that had special application to Cycle 12 of Unit 2 only. Cycle 12 of Unit 2 ended in May 1999. Since these notes no longer have application, they are proposed to be removed. Figure 2.1.1-1a only applies to Cycle 12 of Unit 2 and is proposed to be removed.
Correct a Typographical Error Technical Specification 5.6.5.b, Jtem 41.ii gives the number of the document "BASSS, Use of the incore l Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit I and Unit 2" as CEN-199(B)-P. The actual number is CEN-119(B)-P.
PROPOSED TECHNICAL SPECIFICATION CHANGES Technical Specification 1.1 is proposed to be changed to replace the definition of Azimuthal Power Tilt with a new definition.
l Technical Specification 2.1.1.2 is proposed to be changed by replacing the peak linear heat rate safety limit with s 22 kW/fl.
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-. .,o ATTACHMENT (1)
BACKGROUND AND ANALYSIS Technical Specification SR 3.3.6.2 is proposed to be changed by replacing the degraded voltage function with transient degraded voltage and steady-state degraded voltage functions.
Technical Specification SRs 3.8.1.9 and 3.8.1.15 are proposed to be changed by replacing the steady-state voltage range with the range of;t 4060 volts and s 4400 volts.
Technical Specification 5.6.5.a is proposed to be changed by adding Technical Specifications 3.1.4 and 3.3.1 to the list,'
i Technical Specification Figure 2.1.1-1 is proposed to be changed by removing the reference to Figure B2.1-1.
Various Technical Specifications and Figure 2.1.1-la are proposed to be changed by removing references to Unit 2, Cycle 12, and deleting Figure 2.1.1-la.
Technical Specification 5.6.5.b, Item 41.ii is proposed to be changed by correcting CEN-199(B)-P to
- CEN-119(B)-P.
ANALYSIS :
Change the Definition of Azimuthal Power Tilt ne value of T ,qas used in the azimuthal power tilt formula now in Technical Specification 1.1, is not conservative m all cases.
Calvert Clifts measures the azimuthal tilt using symmetric incore or excore detectors and the CECOR tilt algorithm. With this algorithm, it is assumed that the first azimuthal tilt mode is present and that the ratio of the power in any core location in the presence of a tilt to the untilted or average power at that location is of the form:
Ptilt (r,0) / Pavg (r,0)- 1 = Tq* g (r)
- cos (0 - 00 )
where:
Ptilt (r,0) is the tilted power at radius r and azimuthal angle 0 Pavg (r,0) is the average or untilted power at that location Tq is the azimuthal tilt magnitude g(r) is the radial normalizing factor, normalized to a maximum value of unity 0- is the azimuthal core location 00 is the azimuthal core location of maximum tilt ne definition proposed to be used for azimuthal power tilt is more representative of this concept than the definition currently in Technical Specification 1.1. With this proposed definition, T q is the maximum fractional icrease in power that can occur anywhere in the core because of tilt. Since T q si the maximum value, it is conservative. This is the appropriate measured value of tilt to be used in verifying that the tilt assumed in establishing safety limits has not been exceeded.
The formula expressed above will be added to the basis for Technical Specification 1.1.
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l ATTACHMENT (1) l BACKGROUND AND ANALYSIS i
- i Correct the Peak Linear Heat Rate Safety Limit This proposed amendment to the Technical Specifications was approved by a license amendment and, therefore, does not need further evaluation.
Correct the Diesel Generator Loss of Voltage and Degraded Voltage Settings l This proposed amendment to the Technical Specifications was approved by a license amendment and, l therefore, does not need further evaluation.
Correct the Diesel Generator Voltage Range This proposed amendment to the Technical Specifications was approved by a license amendment and, therefore, does not need further evaluation.
l Correct the List of Core Operating Limits This proposed correction makes the list of Technical Specifications that are to be included in the core l operating limits match the list that existed before ITS conversion. In the ITS conversion, thejustification for changing the list was that it was a change of numbers only. He numbers changed because the )
Technical Specification numbering in ITS is different from the former Technical Specification I
numbering. Sincelhe change was intended to only indicate the new Technical Specification numbers, leaving out two of the specifications was unintentional.
This proposed change will also make the Technical Specification list match the Core Operating Limits Report list.
I Correct Figure 2.1.1-1 l The correct wording of the note in Technical Specification Figure 2.1.1-1 was approved in a license amendment and has not been intentionally changed by a subsequent license amendment. Therefore, this proposed change does not need further evaluation.
Remove References to Unit 2, Cycle 12 The references to Unit 2, Cycle 12, have no application now that Unit 2 is in Cycle 13. The Technical Specifications being changed are equally applicable to both units. Therefore, removal of the notes and deletion of Figure 2.1.1-la are administrative changes.
Correct a Typographical Error 1
Correction of a publication number in Technical Specification 5.6.5.b, item 41.ii is an administrative change.
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ATTACHMENT (2)
DETERMINATION OF SIGNIFICANT HAZARDS i
l Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant September 1,1999
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A'ITACHMENT (2)
DETERMINATION OF SIGNIFICANT HAZARDS The . proposed changes have been evaluated against the standards in 10 CFR 50.92 and have been determined to not involve a significant hazards consideration in that operation of the facility in accordance with the proposed amendments:
- 1. Would not involve a significant increase in the probability or consequences of an accidentpreviously evaluated.
Change the Definition of Azimuthal Power Tilt In their Infobulletin 97-07, Revision 1, Asea Brown Boveri, Inc.-Combustion Engineering, Inc.
(ABB-CE) stated that they had found a discrepancy in the Technical Specification definition of azimuthal power tilt. His discrepancy was found to exist in all CE Nuclear Steam Supply System analog plants that use CECOR for monitoring and surveillance, and that use ABB-CE safety analysis methodology. Calvert Cliffs is one of those plants.
The value of Tq (azimuthal tilt magnitude) as used in the azimuthal power tilt formula now in l Technical Specification 1.1 is not conservative in all cases. With the proposed definition, Tq is the maximum fractional increase in power that can occur anywhere in the core because of tilt. Smce Tq is the maximum value, it is consistently conservative. This is the appropriate measured value of tilt to be used in verifying that the tilt assumed in establishing safety limits has not been exceeded.
Therefore, changing the definition of azimuthal power tilt as proposed will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Correct the Peak Linear Heat Rate Safety Limit When Improved Standard Technical Specifications (ITS) were written, the peak linear heat rate safety limit of s 21 kW/ft was inadvertently written in Technical Specification 2.1.1.2. The correct number is s 22 kW/ft. The peak linear heat rate safety limit was established ats 22 kW/f1 in License Amendment Nos. 88 (Unit 1) and 61 (Unit 2). This number was valid for both units at the time of implementation ofITS.
Therefore, changing the peak linear heat rate safety limit to a number previously approved by the Nuclear Regulatory Commission (NRC) will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Correct the Diesel Generator Loss of Voltage and Degraded Voltage Settings When the ITS were written, a single set of numbers for the degraded voltage function was provided in Technical Specification Surveillance Requirement (SR)3.3.6.2. The degraded voltage function should have been expressed as transient degraded voltage and steady-state degraded voltage. This separation of two types of degraded voltage functions was approved in License Amendment Nos. 226 (Unit 1) and 200 (Unit 2), which were issued before the ITS were approved.
Therefore, changing the degraded voltage function to the transient degraded voltage and steady-state degraded voltage functions previously approved by the NRC will not involve a significant increase in the probability or consequences of an accident previously evaluated.
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A'ITACHMENT (2)
DETERMINATION OF SIGNIFICANT HAZARDS 4
Correct the Diesel Generator Voltage Range Technical Specification SRs 3.8.1.9 and 3.8.1.15 require each diesel to be started from a stand-by condition. Surveillance Requirement 3.8.1.9 requires that the generator reach 2 3740 volts within 10 seconds. After steady-state conditions are reached, both SRs require the generator to maintain a voltage range of > 3740 volts and s 4580 volts.
The Baltimore Gas and Electric Company ITS conversion added voltage requirements to SRs 3.8.1.9 and 3.8.1.15 consistent with SR 3.8.1.3. License Amendment Nos. 226 and 200 changed the voltage requirement for SR 3.8.1.3 to 2 4060 volts and s 4400 volts. The voltage was not corrected in SRs 3.8.1.9 and 3.8.1.15 when the Technical Specifications were changed to ITS.
Therefore, changing the voltage in SRs 3.8.1.9 and 3.8.1.15 to voltage previously approved by the NRC will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Correct the List of Core Operating Limits Technical Specification 5.6.5.a lists Technical Specifications that are to be included in the core operating limits and documented in the Core Operating Limits Report (COLR). In the transition to .
ITS, Technical Specifications 3.1.4 (Control Element Assembly Alignment) and 3.3.1 (Reactor l Protective System - Operating) were inadvenently omitted from the list. The complete list is currently in the COLR.
Therefore, restoring Technical Specification 5.6.5.a to a list previously approved by the NRC will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Correct Figure 2.1.1-1 A note on Technical Specification Figure 2.1.1-1 was changed in License Amendment Nos.227 (Unit 1) and 201 (Unit 2)(ITS) to delete reference to Figure B2.1-1. Figure B2.1-1 was deleted from the Technical Specification Bases in the transition to ITS. In License Amendment Nos. 228 (Unit 1) I and 202 (Unit 2), an old version of Figure 2.1.1-1 was used, and the reference to Figure B2.1-1 was thus inadvertently put back in the note. The proposed correction will replace the reference to Figure B2.1-1 with the wording approved in License Amendment Nos. 227 and 201.
Therefore, returning the note in Figure 2.1.1-1 to the wording previously approved by the NRC will not involve a significant increase in the probability or consequences of an accident previously evaluated.
Remove References to Unit 2, Cycle 12 License Amendment Nos. 228 and 202 added notes to indicate areas in the Technical Specifications that had special application to Cycle 12 of Unit 2 only. Cycle 12 of Unit 2 ended in May 1999. Since these notes no longer have application, they are proposed to be removed. Additionally, Figure 2.1.1-la applies only to Unit 2, Cycle 12, and it is proposed to be removed.
Therefore, removal ofinformation no longer applicable to either unit is an administrative change and will not involve a significant increase in the probability or consequences of an accident previously evaluated.
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DETERMINATION OF SIGNIFICANT HAZARDS Correct a Typographical Error Technical Specification 5.6.5.b, item 41.ii is being corrected to change the number of the publication
! "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit I and l Unit 2" from CEN-199(B)-P to CEN-Il9(B)-P. Correction of a typographical errer does not involve l
a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Would not create the possibility of a new or di[ferent type of accidentfrom any accident previously evaluated.
1 Change the Dennition of Azimuthal Power Tilt in their Infobulletin 97-07, Revision I, ABB-CE stated that they had found a discrepancy in the Technical Specification definition of azimuthal power tilt. This discrepancy was found to exist in all i CE Nuclear Steam Supply System analog plants that use CECOR for monitoring and surveillance and l that use ABB-CE safety analysis methodology. Calvert Cliffs is one of those plants.
The value of Tq(azimuthal tilt magnitude) as used in the azimuthal power tilt formula now in Technical Specification 1.1 is not always the most conservative in all cases. With the proposed i definition, Tq si the maximum fractional increase in power that can occur anywhere in the core l because of tilt. Since T qis the maximum value, it is conservative. This is the appropriate measured value of tilt to be used in verifying that the tilt assumed by ABB-CE in establishing safety limits has not been exceeded.
l Therefore, changing the definition of azimuthal power tilt as proposed will not create the possibility l
of a new or different type of accident from any accident previously evaluated.
Correct the Peak Linear Heat Rate When the ITS were written, a value of peak linear heat rate s 21 kW/ft was inadvertently written in Technical Specification 2.1.1.2. The correct number is s 22 kW/ft. The required peak linear heat i rate was established at s 22 kW/ft in License Amendment Nos. 88 and 61. This number was valid for I
both units at the time ofimplementation ofITS. l l
Therefore, changing the value of the peak linear heat rate to a value previously approved by the NRC will not create the possibility of a new or different type of accident from any accident previously evaluated.
Correct the Diesel Generator Loss of Voltage and Degraded Voltage Settings When the ITS were written, a single set of numbers for the degraded voltage function was provided in Technical Specification SR 3.3.6.2. The degraded voltage function should have been expressed as transient degraded voltage and steady-state degraded voltage. This separation of two types of degraded voltage fimetions was approved in License Amendment Nos.226 and 200, which were issued before the ITS were approved.
Therefore, changing the degraded voltage function to the transient degraded voltage and steady-state degraded voltage functions previously approved by the NRC will not create the possibility of a new i or different type of accident from any accident previously evaluated.
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A'ITACllMENT (2)
DETERMINATION OF SIGNIFICANT IIAZARDS Correct the Diesel Generator Voltage Range Technical Specification SRs 3.8.1.9 and 3.8.1.15 require that each diesel be started from a stand-by condition. Surveillance Requirement 3.8.1.9 requires that the generator reach 2 3740 volts within 10 seconds. After steady-state conditions are reached, both SRs require the generator to maintain a voltage range of> 3740 volts ar.d s 4580 volts.
The Baltimore Gas and Electric Company ITS conversion added voltage requirements to SRs 3.8.1.9 and 3.8.1.15 consistent with SR 3.8.1.3. License Amendments Nos. 226 and 200 changed the voltage requirement for SR 3.8.1.3 to 24060 volts and s 4400 volts. The voltage was not corrected in SRs 3.8.1.9 and 3.8.1.15 when the Technical Specifications were changed to ITS.
Therefore, changing the voltage in SRs 3.8.1.9 and 3.8.1.15 to a voltage previously approved by the NRC will not create the possibility of a r.ew or different type of accident from any accident previously evaluated.
Correct the List of Core Operating Limits Technical Specification 5.6.5.a lists Technical Specifications that are to be included in the core operating limits and documented in the COLR. In the transition to ITS, Technical Specifications 3.1.4 (Control Element Assembly Alignment) and 3.3.1 (Reactor Protective System -
Operating) were inadvertently omitted from the list. The complete list is currently in the COLR.
Therefore, restoring Technical Specification 5.6.5.a to a list previously approved by the NRC will not create the possibility of a new or different type of accident from any accident previously evaluated.
Correct Figure 2.1.1 1 A note on Technical Specification Figure 2.1.1-1 was changed in License Amendment Nos. 227 and 201 (ITS) to delete reference to Figure B2.1-1. Figure B2.1-1 was deleted from the Technical Specification Bases in the transition to ITS. In License Amendment Nos. 228 and 202, an old version of Figure 2.1.1-1 was used, and the reference to Figure B2.1-1 was thus inadvertently put back in the i
note. The proposed correction will replace the reference to Figure B2.1-1 with the wording approved I in License Amendment Nos. 227 and 201. l Therefore, returning the note in Figure 2.1.1-1 to the wording previously approved by the NRC will i not create the possibility of a new or different type of accident from any accident previously evaluated.
Remove References to Unit 2, Cycle 12 License Amendment Nos. 228 and 202 added notes to indicate areas in the Technical Specifications that had special application to Cycle 12 of Unit 2 only. Cycle 12 of Unit 2 ended in May 1999. Since these notes no longer have application, they are proposed to be removed. Additionally, Figure 2.1.1- l la applies only to Unit 2, Cycle 12, and is proposed to be removed. ,
Therefore, removal ofinformation no longer applicable to either unit is an administrative change and will not create the possibility of a new or different type of accident from any accident previously evaluated.
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m ATTACIIMENT (2) i DETERMINATION OF SIGNIFICANT IIAZARDS
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Correct a Typographical Error Technical Specification 5.6.5.b, Jtem 41.ii is being corrected to change the number of the publication "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit I and Unit 2" from CEN-199(B)-P to CEN-119(B)-P. Correction of a typographical error will not create the pc,ssibility of a new or different type of accident from any accident previously evaluated.
- 3. Would not involve a sigraficant reduction in the margin ofsafety.
Change the Definition of Azimuthal Power Tilt The margin of safety in this case is whether the azimuthal power tilt calculation shows the highest I (most conservative) value for Tq (azimuthal tilt magnitude).
The value of Tqas used in the azimuthal power tilt formula now in Technical Specification 1.1 is not always the most conservative in all cases. With the proposed definition, Tq si the maximum fractional increase in power that can occur anywhere in the core because of tilt. Since Tq is the maximum value, it is conservative. This is the appropriate measured value of tilt to be used in verifying that the tilt assumed in establishing safety limits has not been exceeded.
Therefore, changing the definition of azimuthal power tilt as proposed will not involve a significant reduction in the margin of safety.
Correct the Peak Linear lient Rate Safety Limit The margin of safety in this case was previously approved by the NRC in License Amendment Nos. 88 and 61. j Correct the Diesel Generator Loss of Voltage and Degraded Voltage Settings The margin of safety in this case was previously approved by the NRC in License Amendment Nos. 226 and 200.
Correct the Diesel Generator Voltage Range The margin of safety in this case was previously approved by the NRC in License Amendment Nos. 226 and 200.
Correct the List of Core Operating Limits Technical Specification 5.6.5.a lists Technical Specifications that are to be included in the core operating limits and documented in the COLR. In the transition to ITS, Technical Specifications 3.L4 (Control Element Assembly Alignment) and 3.3.1 (Reactor Protective System -
Operating) were inadvertently omitted from the list. The complete list is currently in the COLR.
Therefore, restoring Technical Specification 5.6.5.a to a list previously approved by the NRC will not involve a significant reduction in the margin of safety.
Correct l'igure 2.1.1-1, A note en Technical Specification Figure 2.1.1-1 was changed in License Amendment Nos. 227 and 201 (ITS) to delete reference to Figure B2.1-1. Figure B2.1-1 was deleted from the Technical Specification Bases in the transition to ITS. In License Amendment Nos. 228 and 202, an old version 6
j ATTACHMENT (2)
DETERMINATION OF SIGNIFICANT HAZARDS i.
of Figure 2.1.1-1 was used, and the reference to Figure B2.1-1 was thus inadvertently put back in the note. The proposed correction will replace the reference to Figure B2.1-1 with the wording approved in License Amendment Nos. 227 and 201.
Therefore, retucning the note in Figure 2.1.1-1 to the wording previously approved by the NRC will not involve a signi6 cant reduction in the margin of safety.
Remove References to Unit 2, Cycle 12 License Amendment Nos. 228 and 202 added notes to indicate areas in the Technical Speci6 cations that had special application to Cycle 12 of Unit 2 only. Cycle 12 of Unit 2 ended in May 1999. Since these noteu no longer have application, they are proposed to be removed. Additionally, Figure 2.1.1-la applies only to Unit 2, Cycle 12, and it is proposed to be removed.
l Therefore, removal of information no longer applicable to either unit is an administrative change and 1 will not involve a significant reduction in the margin of safety.
Correct a Typographical Error l Technical Specification 5.6.5.b, Item 41.ii is being corrected to change the number of the publication "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit I and Unit 2" from CEN-199(B)-P to CEN-119(B)-P. Correction of a typographical error will not involve a significant reduction in the margin of safety.
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