ML061780165
| ML061780165 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/09/2006 |
| From: | Gordon Peterson Duke Energy Carolinas, Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| MC-GRP-01 | |
| Download: ML061780165 (51) | |
Text
PDuke aEnergy June 9, 2006 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C.
20555-0001 GARY R. PETERSON Vice President McGuire Nuclear Station Duke Energy Corporation MGO1VP / 12700 Hagers Ferry Rd.
Huntersville, NC 28078 704 875 5333 704 875 4809 fax grpeters@duke-energy.com
Subject:
Reference:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC (Duke)
McGuire Nuclear Station - Units 1 & 2 Docket Nos. 50-369, 50-370 Inservice Testing Program Request for Additional Information (RAI)
Relief Request Nos. MC-GRP-01 (1) Letter from Mr. G.R. Peterson of Duke Power to NRC, dated August 12,
- 2004, (2) Letter from Mr.
G.R. Peterson of Duke Power to NRC, dated November 18, 2004, (3) Letter from Mr. James J.
Shea of the NRC to Mr. G.R. Peterson of Duke Power, dated April 8,
2005, and (4)
Letter from Mr. G.R. Peterson of Duke Power to NRC, dated June 9, 2005.
Per guidance from the NRC staff, Duke is submitting specific relief requests for each individual pump group-by system in place of the previously submitted generic relief request concerning pump vibration acceptance criteria.
The new relief requests also revise the vibration threshold from 0.075 in/sec to 0.05 in/sec.
Therefore, Relief Request No. MC-GRP-01 is being withdrawn.
Attachment No.
1 includes tables that identify inservice testing program relief requests requiring NRC approval.
These tables provide information pertaining to pump description, test type, testing frequency, ASME class, etc.
Attachments Nos.
2 through 13 are the new relief requests being submitted for approval.
Questions with respect to this matter should be directed to Norman T. Simms of Regulatory Compliance at 704-875-4685.
Sincerely, G.R. Peterson Attachments www.duke-energy.com rn
P U.S. Nuclear Regulatory Commission June 9, 2006 Page 2 xc:
W.D. Travers U.S. Nuclear Regulatory Commission, Region II Atlanta Federal Center 61 Forsyth St.,
SW, Suite 23 T85 Atlanta, GA 30303 J.F. Stang, Jr. (Addressee only)
NRC Project Manager (MNS)
U.S. Nuclear Regulatory Commission One White Flint North, MS 08 H4A 11555 Rockville Pike Rockville, MD 20852-2738 J.B. Brady NRC Senior Resident Inspector McGuire Nuclear Station
ATTACHMENT 1 TABLES
6' Pump Pump ASME Test Relief Equipment ID Description Flow Diagram Group Type Class Type Freq Request CA Auxiliary Feedwater 1CAPUOOO1 Motor Driven Auxiliary Feedwater Pump 1A MC1592.1.1 B
CT 3
Flow/Differential Pressure Test Q
None Vibration Test 2Y MC-SRP-CA-02 Comprehensive Test 2Y None 1CAPU0002 Motor Driven Auxiliary Feedwater Pump 1 B MC-1592-1.1 B
CT 3
Flow/Differential Pressure Test Q
None Vibration Test 2Y MC-SRP-CA-02 Comprehensive Test 2Y None 1CAPri0003 Tiirhinn fridvin Aityili~nr, lortw~tnr P,,mn ik1 I*AC'1. O
=
_I D
('T n
',.1:*...
2CAPU0001 Motor Driven Auxiliary Feedwater Pump 2A 2CAPUOOO2 Motor Driven Auxiliary Feedwater Pump 2B 2CAPU0003 Turbine Driven Auxiliary Feedwater Pump #2 MC-2592-1.1 MC-2592-1.1 MC-2592-1.1 U
%J I a
b UI 3
r'uwIuierential rressure lest Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test U
2Y 2Y Q
2Y 2Y Q
2Y 2Y Q
2Y 2Y None MC-SRP-CA-03 None None MC-SRP-CA-02 None None MC-SRP-CA-02 None None MC-SRP-CA-03 None D
ta I 3
13 U1 3
2Y McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 1
-V Pump Pump ASME Test Relief Equipment ID Description Flow Diagram Group Type Class Type Freq Request KC -
Component Cooling 1KCPUOOOI Component Cooling Water Pump I A MC-1573-1.0 A
CT 3
Flow/Differential Pressure Test Q
MC-SRP-KC-OI Vibration Test 0
MC-SRP-KC-02 Comprehensive Test 2Y None 1KCPUO002 Component Cooling Water Pump 1A2 MC-1573-1.0 A
CT 3
Flow/Differential Pressure Test Q
MC-SRP-KC-01 Vibration Test Q
MC-SRP-KC-02 Comprehensive Test 2Y None 1KCPUO003 Component Cooling Water Pump 1B1 MC-1573-1.0 A
CT 3
Flow/Differential Pressure Test Q
MC-SRP-KG-01 Vibration Test Q
MC-SRP-KC-02 Comprehensive Test 2Y None 1 KCPU0004 Component Cooling Water Pump 1B2 MC-1573-1.0 A
CT 3
Flow/Differential Pressure Test Q
MC-SRP-KC-01 Vibration Test Q
MC-SRP-KC-02 Comprehensive Test 2Y None 2KCPUOOOI Component Cooling Water Pump 2A1 MC-2573-1.0 A
CT 3
Flow/Differential Pressure Test Q
MC-SRP-KC-01 Vibration Test Q
MC-SRP-KC-02 Comprehensive Test 2Y None 2KCPUO002 Component Cooling Water Pump 2A2 MC-2573-1.0 A
CT 3
Flow/Differential Pressure Test Q
MC-SRP-KC-01 Vibration Test 0
MC-SRP-KC-02 Comprehensive Test 2Y None 2KCPUO003 Component Cooling Water Pump 2B1 M0-2573-1.0 A
CT 3
Flow/Differential Pressure Test Q
MC-SRP-KC-01 Vibration Test Q
MC-SRP-KC.02 Comprehensive Test 2Y None 2KCPUO004 Component Cooling Water Pump 2B2 MC-2573-1.0 A
CT 3
Flow/Differential Pressure Test Q
MC-SRP-KC-01 Vibration Test Q
MC-SRP-KC-02 Comprehensive Test 2Y None McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 2
Pump Pump ASME Test Relief Equipment ID Description Flow Diagram Group Type Class Type Freq Request ND-Residual Heat Removal and Low Head Safety Injection 1NDPUOOO1 Residual Heat Removal Pump 1A MO-1561-1.0 A
CT 2
Flow/Differential Pressure Test Q
MC-SRP-ND-01 Vibration Test 0
MC-SRP-ND-02 Comprehensive Test 2Y None 1NDPU0002 Residual Heat Removal Pump 1B MC-1561-1.0 A
CT 2 -
Flow/Differential Pressure Test Q
MC-SRP-ND-01 Vibration Test Q
MC-SRP-ND-02 Comprehensive Test 2Y None 2NDPU0001 Residual Heat Removal Pump 2A MC-2561-1.0 A
CT 2
Flow/Differential Pressure Test Q
MC-SRP-ND-01 Vibration Test Q
MC-SRP-ND-02 Comprehensive Test 2Y None 2NDPU0002 Residual Heat Removal Pump 2B MC-2561-1.0 A
CT 2
Flow/Differential Pressure Test Q
MC-SRP-ND-01 Vibration Test 0
MC-SRP-ND-02 Comprehensive Test 2Y None McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 3
Pump Pump ASME Test Relief Equipment ID Description Flow Diagram Group Type Class Type Freq Request NI-Medium Head Safety Injection 1NIPU0009 Safety Injection Pump 1A MC-1562-3.0 A
CT 2
Flow/Differential Pressure Test Q
None Vibration Test a
MC-SRP-NI-02 Comprehensive Test 2Y None 1NIPU0010 Safety Injection Pump 1B MC-1562-3.0 A
CT 2
Flow/Differential Pressure Test 0
None Vibration Test a
MC-SRP-NI-02 Comprehensive Test 2Y None 2NIPU0009 Safety Injection Pump 2A MG-2562-3.0 A
CT 2
Flow/Differential Pressure Test 0
None Vibration Test 0
MC-SRP-NI-02 Comprehensive Test 2Y None 2NIPU0010 Safety Injection Pump 2B MG-2562-3.0 A
CT 2
Flow/Differential Pressure Test 0
None Vibration Test 0
MC-SRP-NI-02 Comprehensive Test 2Y None McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 4
-0 Pump Pump ASME Test Relief Equipment ID Description Flow Diagram Group Type Class Type Freq Request NS -
Containment Spray 1NSPUOOO1 Containment Spray Pump 1A MC.1563-1.0 B
CT 2
Flow/Differential Pressure Test 0
None Vibration Test 2Y MC.SRP-NS-02 Comprehensive Test 2Y None 1NSPUO002 Containment Spray Pump 1B MC-1563-l.0 B
CT 2
Flow/Differential Pressure Test Q
None Vibration Test 2Y MC-SRP-NS-02 Comprehensive Test 2Y None 2NSPUOOO1 Containment Spray Pump 2A MC-2563-1.0 B
CT 2
Flow/Differential Pressure Test Q
None Vibration Test 2Y MC-SRP-NS-02 Comprehensive Test 2Y None 2NSPUO002 Containment Spray Pump 2B MC-2563-1.0 B
CT 2
Flow/Ditferential Pressure Test 0
None Vibration Test 2Y MC-SRP-NS-02 Comprehensive Test 2Y None McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 5
-I Pump Pump ASME Test Relief Equipment ID Description Flow Diagram Group Type Class Type Freq Request NV -
Chemical & Volume Control 1NVPU0015 Centrifugal Charging Pump 1A 1NVPU0016 Centrifugal Charging Pump 1B 1NVPU0027 Boric Acid Transfer Pump 1A 1NVPU0028 Boric Acid Transfer Pump 1 B 2NVPU0015 Centrifugal Charging Pump 2A 2NVPU0016 Centrifugal Charging Pump 2B 2NVPU0027 Boric Acid Transfer Pump 2A 2NVPU0028 Boric Acid Transfer Pump 2B MC-1554-1.0 MC-1554-1.0 MC-1554-5.0 MC-1554-5.0 MC-2554-1.0 MC-2554-1.0 MC-2554-5.0 MC-2554-5.0 A
^
Flow/L)itterential Pressure lest Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Dilferential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test U
Q 2Y Q
2Y Q
Q 2Y Q
Q 2Y Q
Q 2Y Q
Q 2Y Q
Q 2Y a
Q 2Y None MC-SRP-NV-02 None None MC-SRP-NV-02 None None MC-SRP-NV-03 None None MC-SRP-NV-03 None None MC-SRP-NV-02 None None MC-SRP-NV-02 None None MC-SRP-NV-03 None None MC-SRP-NV-03 None A
^
McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 6
pf Equipment ID Description RN -
Nuclear Service Water 1RNPU0003 Nuclear Service Water Pump 1A 1RNPUO004 Nuclear Service Water Pump 1B 2RNPU0003 Nuclear Service Water Pump 2A 2RNPU0004 Nuclear Service Water Pump 2B Pump Pump ASME Test Relief Flow Diagram Group Type Class Type Freq Request MC-1574-1.1 MO-1574-1.1 MC-2574-1.1 MC-2574-1.1 A
- T A
A A
3w Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test.
Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Q
Q 2Y Q
Q 2Y 0
Q 2Y 0
Q 2Y None MC-SRP-RN-02 None None MC-SRP-RN-02 None None MC-SRP-RN-02 None None MC-SRP-RN-02 None McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 7
e.
Pump Pump ASME Test Relief Equipment ID Description Flow Diagram Group Type Class Type Freq Request WN - Diesel Generator Room Sump Pump 1WNPU0094 Diesel Generator Sump Pump 1A2 MC 1WNPU0095 Diesel Generator Sump Pump 1B2 MC 1WNPU0096 Diesel Generator Sump Pump 1A3 MC 1WNPU0097 Diesel Generator Sump Pump 1B3 MC 2WNPU0094 Diesel Generator Sump Pump 2A2 MC 2WNPU0095 Diesel Generator Sump Pump 2B2 MC 2WNPU0096 Diesel Generator Sump Pump 2A3 MC 2WNPU0097 Diesel Generator Sump Pump 283 MC
~1609-7.0
~1609-7.0
,-1 609-7.0
ý1 609-7.0
~-2609-7.0
-2609-7.0
~-2609-7.0
~-2609-7.0 B
Bw Bw CT CT CT CT CT CT CT CT B
B B
B 3
Vibration Test Comprehensive Test 3
Vibration Test Comprehensive Test 3
Vibration Test Comprehensive Test 3
Vibration Test Comprehensive Test 3
Vibration Test Comprehensive Test 3
Vibration Test Comprehensive Test 3
Vibration Test Comprehensive Test 3
Vibration Test Comprehensive Test 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y 2Y
^,,
MC-SRP-WN-01 None MC-SRP-WN-01 None MC-SRP-WN-01 None MC-SRP-WN-01 None MC-SRP-WN-01 None MC-SRP.WN-01 None MC-SRP-WN-01 None MC-SRP-WN-01 None McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 8
.4 Equipment ID Description WZ -
Groundwater Monitoring and OWZPUG001 Groundwater Drainage Sump A Pump A OWZPU0002 Groundwater Drainage Sump A Pump 8 OWZPU0003 Groundwater Drainage Sump B Pump A OWZPU0004 Groundwater Drainage Sump 8 Pump B OWZPU0005 Groundwater Drainage Sump C Pump A OWZPU0006 Groundwater Drainage Sump C Pump B Pump Pump ASME Test Relief Flow Diagram Group Type Class Type Freq Request Sump MLIDOI-1.U MC-1581-1.0 MC-1581-1.0 MC.1581-1.0 MC-1581.1.0 MG.1581.1.0 A
A A
A A
A U'
3
-w 3w 3
rlow/uifrerenial rFressure I est Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test Flow/Differential Pressure Test Vibration Test Comprehensive Test U
Q 2Y Q
a 2Y 0
2Y 0
2Y a
Q 2Y 0
a 2Y None MC-SRP-WZ-01 None None MC-SRP-WZ-01 None None MC.SRP-WZ-01 None None MC-SRP.WZ-01 None None MC.SRP-WZ-01 None None MC-SRP-WZ-O1 None McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 9
Pump Pump ASME Test Relief Equipment ID Description Flow Diagram Group Type Class Type Freq Request YC -
Control Area Chilled Water OYCPU0003 Control Area Chilled Water Pump Train A MC-1618-1 A
CT 3
Flow/Diflerential Pressure Test Q
None Vibration Test 0
MC-SRP-YC-01 Comprehensive Test 2Y None OYCPU0004 Control Area Chilled Water Pump Train B MG-1618-1 A
CT 3
Flow/Differential Pressure Test Q
None Vibration Test a
MC-SRP-YC-o0 Comprehensive Test 2Y None McGuire Nuclear Station IST Program Submittal - Pumps Revision 27 (05/10/06)
Section 3.1 Page 10
5.1 PUMP GENERIC RELIEF REOUESTS Relief Request Applicability Status none Rev. 27 05/10/06 Page 1 of I
5.2 PUMP SPECIFIC RELIEF REQUESTS Relief Request MC-SRP-CA-01 MC-SRP-CA-02 MC-SRP-CA-03 MC-SRP-FD-01 MC-SRP-KC-01 MC-SRP-KC-02 MC-SRP-ND-01 MC-SRP-ND-02 MC-SRP-NI-01 MC-SRP-NI-02 MC-SPR-NS-02 MC-SRP-NV-01 MC-SRP-NV-02 MC-SRP-NV-03 MC-SRP-RN-01 MC-SRP-RN-02 MC-SRP-WN-01 MC-SRP-WZ-OI MC-SRP-YC-01 Applicability Auxiliary Feedwater Pumps Motor Driven Auxiliary Feedwater Pumps Turbine Driven Auxiliary Feedwater Pumps Diesel Generator Fuel Oil Pumps Component Cooling Pumps Component Cooling Pumps Residual Heat Removal Pumps Residual Heat Removal Pumps Safety Injection Pumps Safety Injection Pumps Containment Spray Pumps Chemical & Volume Control Pumps Centrifugal Charging Pumps Boric Acid Transfer Pumps Nuclear Service Water Pumps Nuclear Service Water Pumps Diesel Generator Sump Pumps Groundwater Drainage Sump Pumps Control Room Chilled Water Pumps Status Deleted Revision 26 Added-Revision 27 Added-Revision 27 DELETED-Revision 27 Revised-Revision 27 Added-Revision 27 Revised-Revision 27 Added-Revision 27 DELETED-Revision 27 Added-Revision 27 Added-Revision 27 DELETED-Revision 27 Added-Revision 27 Added-Revision 27 Deleted-Revision 22 Added Revision 27 Added Revision 27 Added Revision 27 Added Revision 27 Rev. 27 05/10/06 Page 1 of I
ATTACHMENT 2 MC-SRP-CA-02
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-CA-02 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected ICAPU0001, IA CA (Auxiliary Feedwater) Pump 1CAPU0002, lB CA Pump 2CAPU0001, 2A CA Pump 2CAPU0002, 2B CA Pump
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraph ISTB-5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to *0.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
05/10/06 MC-SRP-CA-02 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-CA-02 Rev.27 Page 2 of 2 Section 5.1
"b ATTACHMENT 3 MC-SRP-CA-03
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-CA-03 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected 1CAPU0003, Unit 1 Turbine Driven CA (Auxiliary Feedwater) Pump 2CAPU0003, Unit 2 Turbine Driven CA Pump
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraph ISTB-5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.'
5. Proposed Alternative and Basis for Use
Anytime Vr *0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to *0.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for 05/10/06 MC-SRP-CA-03 Rev.27 Page I of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-CA-03 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 4 MC-SRP-KC-02
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-KC-02 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected 1KCPU0001, KC (Component Cooling Water) Pump IAl 1KCPU0002, KC Pump 1A2 1KCPU0003, KC Pump IB1 1KCPU0004, KC Pump 1B2 2KCPUOO01, KC Pump 2AI 2KCPU0002, KC Pump 2A2 2KCPU0003, KC Pump 2B 1 2KCPU0004, KC Pump 2B2
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraphs ISTB-5121(e) and 5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Group A and Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to 50.300 in/sec 05/10/06 MC-SRP-KC-02 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, M1B6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-KC-02 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 5 MC-SRP-ND-02
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-ND-02 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected INDPU0001, ND (Residual Heat Removal) Pump IA INDPU0002, ND Pump lB 2NDPUOOO1, ND Pump 2A 2NDPU0002, ND Pump 2B
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraphs ISTB-5121(e) and 5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Group A and Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr
- 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to _0.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
05/10/06 MC-SRP-ND-02 Rev.27 Page I of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-ND-02 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 6 MC-SRP-NI-02
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-NI-02 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected 1NIPU0009, NI (Safety Injection ) Pump IA 1NIPU0010, NI Pump 1B 2NIPU0009, NI Pump 2A 2NIPU0010, NI Pump 2B
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraphs ISTB-5121(e) and 5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Group A and Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to 50.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
05/10/06 MC-SRP-NI-02 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 By applying the above alternative criteria to only those pumps With vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-NI-02 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 7 MC-SRP-NS-02
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-NS-02 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected 1NSPU0001, NS (Containment Spray ) Pump 1A INSPU0002, NS Pump 1B 2NSPU0001, NS Pump 2A 2NSPU0002, NS Pump 2B
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraph ISTB-5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to <0.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
05/10/06 MC-SRP-NS-02 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-NS-02 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 8 MC-SRP-NV-02
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-sRP-NV-02 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected 1NVPU0015, NV (Centrifugal Charging) Pump IA 1NVPU0016, NV Pump 1B 2NVPUOO15, NV Pump 2A 2NVPUOO16, NV Pump 2B
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraphs ISTB-5121(e) and 5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Group A and Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5 100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to <0.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
05/10/06 MC-SRP-NV-02 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 By applying the above alternativ6,criteria to only those pumPio With vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-NV-02 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 9 MC-SRP-NV-03
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-NV-03 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected 1NVPU0027, BAT (Boric Acid Transfer) Pump IA 1NVPU0028, BAT Pump 1B 2NVPU0027, BAT Pump 2A 2NVPU0028, BAT Pump 2B
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraphs ISTB-5121(e) and 5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Group A and Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to *0.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
05/10/06 MC-SRP-NV-03 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-NV-03 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 10 MC-SRP-RN-02
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-RN-02 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected 1RNPU0003, RN (Nuclear Service Water) Pump IA 1RNPU0004, RN Pump 1B 2RNPU0003, RN Pump 2A 2RNPU0004, RN Pump 2B
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraphs ISTB-5121(e) and 5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Group A and Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to *0.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
05/10/06 MC-SRP-RN-02 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-RN-02 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 11 MC-SRP-WN-01
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-WN-01 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected IWNPU0094, WN (Diesel Generator Sump) Pump 1A2 lWNPU0095, WN Pump 1B2 IWNPU0096, WN Pump 1A3 lWNPU0097, WN Pump 1B3 2WNPU0094, WN Pump 2A2 2WNPU0095, WN Pump 2B2 2WNPU0095, WN Pump 2A3 2WNPU0095, WN Pump 2B3
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraph ISTB-5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/see Alert Range >0.125 to *0.300 in/sec 05/10/06 MC-SRP-WN-01 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-WN-01 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 12 MC-SRP-WZ-01
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-WZ-01 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected 1WZPU0001, WZ (Groundwater Drainage) Sump A Pump A 1WZPU0002, WZ Sump A Pump B IWZPU0003, WZ Sump B Pump A lWZPU0004, WZ Sump B Pump B IWZPU0005, WZ Sump C Pump A 1WZPU0006, WZ Sump C Pump B
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraphs ISTB-5121(e) and 5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Group A and Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to <0.300 in/sec Required Action Range High > 0.300 in/sec 05/10/06 MC-SRP-WZ-01 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-WZ-01 Rev.27 Page 2 of 2 Section 5.1
ATTACHMENT 13 MC-SRP-YC-01
McGuire Unit 1 McGuire Unit 2 10 CFR 50.55a Request Number MC-SRP-YC-01 Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i)
--Alternative Provides Acceptable Level of Quality and Safety--
- 1. ASME Code Components Affected OYCPU0001, YC (Control Room Chilled Water) Pump A OYCPU0002, YC Pump B
2. Applicable Code Edition and Addenda
ASME Code for Operation and Maintenance of Nuclear Power Plants, 1998 Edition through 2000 Addenda (OMb 2000).
3. Applicable Code Requirement
Section IST, Subsection ISTB, Paragraphs ISTB-5121(e) and 5123(e). All deviations from the reference values shall be compared with the ranges of Table ISTB-5100-1 and corrective action taken as specified in ISTB-6200.
Table ISTB-5100-1 Centrifugal Pump Test Acceptance Criteria (applicable vibration ranges only):
Group A and Comprehensive Tests
>600 rpm Acceptable Range <2.5Vr Alert Range >2.5Vr to 6 Vr Required Action Range High >6Vr.
4. Reason for Request
Experience has shown that smooth operating pumps with Vr < 0.05 in/sec often fall in the alert range of vibration measurement of Table ISTB-5100-1. This is not an indication of degraded pump operation but rather a function of multiplying a very small number (<0.05) by 2.5 which results in another small number for the acceptance criteria. The required actions for exceeding the existing acceptance criteria for these pumps are of no value since there is no adverse condition to correct.
5. Proposed Alternative and Basis for Use
Anytime Vr < 0.05 in/sec the following acceptance criteria shall be used:
Acceptable Range <0.125 in/sec Alert Range >0.125 to 50.300 in/sec Required Action Range High > 0.300 in/sec For Vr >0.05 in/sec the existing acceptance criteria of Table ISTB-5200-1 shall be used.
By applying the above alternative criteria to only those pumps with vibration references
<0.05 in/sec the scope is bounded and will not effect the criteria or corrective actions for 05/10/06 MC-SRP-YC-01 Rev.27 Page 1 of 2 Section 5.1
McGuire Unit 1 McGuire Unit 2 any non smooth operating pumps. Also this alternative vibration criteria has been shown by experience to provide an acceptable level for ensuring that pump degradation will be detected and appropriate actions initiated to correct the condition. The affected pumps are also in the Predictive Maintenance Program which provides supplemental information to assure detection of pump degradation. This program provides additional monitoring for these pumps including advanced vibration monitoring techniques (bearing high frequency detection and spectral analysis for the pump as well as the driver). In addition, lubricant analysis for wear debris, chemical composition and cleanliness is performed on these pumps. This alternative provides an acceptable level of quality and safety to that of the existing Code requirement.
6. Duration of Proposed Alternative
This alternative will be used for the entire 3rd 10 year interval for McGuire.
- 7. Precedents (Optional)
Oconee Nuclear Station, (DOC NOs 50-269,-270,-287) submitted generic relief request ON-GRP-01 with identical test alternatives which was approved by NRC (TAC NOs MB6602, MB6603, and MB6604). Palo Verde Nuclear Generating Station (DOC NOs 50-528,-529,-530) also submitted generic relief request PRR-08 with similar test alternatives which was approved by NRC (TAC NOs MA0757, MA0758, and MA0759).
Similar generic relief request MC-GRP-01 was granted by NRC under the previous McGuire submittal with a threshold of 0.075 in/sec. However, during a July 7, 2005 NRC/Duke conversation via phone, NRC advised they would not approve a threshold of greater than 0.05 in/sec nor would they approve a generic relief request.
- 8. References (Optional) n/a 05/10/06 MC-SRP-YC-01 Rev.27 Page 2 of 2 Section 5.1