ML060580081
| ML060580081 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/25/2006 |
| From: | Mauldin D Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-05404-CDM/TNW/RKR | |
| Download: ML060580081 (9) | |
Text
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i-I-AFS 10 CFR 50.90 David Mauldin Vice President Nuclear Engineering Tel: 623-393-5553 and Support Fax: 623-393-6077 Palo Verde Nuclear Generating Station Mail Station 7605 PO Box 52034 Phoenix, Arizona 85072-2034 102-05404-CDM/TNW/RKR January 25, 2006 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Reference:
Letter 102-05223, dated March 4, 2005, from D. Mauldin, APS, to NRC, "Request for Amendment to Facility Operating Licenses NPF-41, NPF-51 and NPF-74 to License Condition 2.F (2.G in Unit 3) and Request for Amendment to Technical Specifications: 1.4, 'Frequency,' 2.1.1, 'Reactor Core SLs,' 3.1.10, 'Special Test Exceptions (STE)- MODES 1 and 2,'
3.3.1, 'Reactor Protective System (RPS) Instrumentation - Operating,'
3.4.3, 'RCS Pressure and Temperature (P/T) Limits,' 3.7.2, 'Main Steam Isolation Valves (MSIVs),' 3.7.3, 'Main Feedwater Isolation Valves (MFIVs),' 3.8.1, 'AC Sources - Operating,' 3.8.4, 'DC Sources -
Operating,' 3.8.6, 'Battery Cell Parameters,' and 5.5.9, 'Steam Generator (SG) Tube Surveillance Program' "
Dear Sirs:
Subject:
Supplement to Provide Updated Technical Specification Pages for the Proposed Operating License Amendment Submitted to the NRC on March 4, 2005 (letter no. 102-05223)
In the referenced letter, Arizona Public Service Company (APS) submitted to NRC a request to amend PVNGS Technical Specifications (TS). Since that submittal, the NRC issued Amendment No. 156 to PVNGS Units 1, 2, and 3. That resulted in the need to update a TS page in the referenced letter. In addition, four of the submitted pages have editorial errors that should be corrected prior to issue of the proposed amendment.
Enclosed are revised proposed retyped -rs pages 2.0-1, 3.7.3-1, 3.8.4-2, 3.8.4-4, and 5.5-15. These pages include the changes proposed in the referenced letter amendment request and the changes approved in Amendment No. 156. No new TS changes are being proposed by this letter. Please use these pages in place of the pages submitted in the referenced TS amendment request letter.
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Supplement to Provide Updated Technical Specification Pages for the Proposed Operating License Amendment Submitted to the NRC on March 4, 2005 (102-05223)
Page 2 No commitments are being made to the NRC by this letter.
Should you have any questions, please contact Thomas N. Weber at (623) 393-5764.
Sincerely, CDM/TNWIRKR/ca
Enclosures:
- Enclosure I - Notarized Affidavit
- Enclosure 2 - Revised Proposed Retyped TS Pages 2.0-1, 3.7.3-1, 3.8.4-2, 3.8.4-4, and 5.5-15 cc:
B. S. Mallett M. B. Fields G. G. Wamick A. V. Godwin NRC Region IV Regional Administrator NRC NRR PrDject Manager NRC Senior Resident Inspector for PVNGS Arizona Radiation Regulatory Agency (ARRA)
STATE OF ARIZONA
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) ss.
COUNTY OF MARICOPA )
1, David Mauldin, represent that I am Vice President Nuclear Engineering and Support, Arizona Public Service Company (APS), that the foregoing document has been signed by me on behalf of APS with full authority to do so, and that to the best of my knowledge and belief, the statements made therein are true and correct.
David Mauldin Sworn To Before Me This.ogDay Of (iiALLIe, 2006.
chblic A /1. /
U SlSIE LYNN ERGGSH Notary Pubic -Afizona mdcopiCounty My Comm. ExpIrel Ad14.2007 Notary Commission Stamp Revised Proposed Retyped TS Pages 2.0-1, 3.7.3-1, 3.8.4-2, 3.8.4-4, and 5.5-15
SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 In MODES 1 and 2, Departure from Nucleate Boiling Ratio (DNBR) shall be maintained at Ž 1.34.
2.1.1.2 In MODES 1 and 2, the peak fuel centerline temperature shall be maintained < 50800F (decreasing by 580F per 10.000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A).
2.1.2 Reactor Coolant System (RCS) Pressure SL In MODES 1, 2. 3. 4. and 5. the RCS pressure shall be maintained at < 2750 psia.
2.2 SL Violations 2.2.1 If SL 2.1.1.1 or SL 2.:L.1.2 is violated, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2 If SL 2.1.2 is violated:
2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
2.2.2.2 In MODE 3. 4. or 5. restore compliance within 5 minutes.
2.2.3 Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, notify the NRC Operations Center, with 10 CFR 50.72.
2.2.4 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the Director, Operations Vice President, Nuclear.
in accordance and the Senior (continued)
PALO VERDE UNITS 1,2.3 2.0-1 AMENDMENT NO. 1469
MFIVs 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Main Feedwater Isolation Va-lves (MFIVs)
LCO 3.7.3 APPLICABILITY:
Four economizer MFIVs and four downcomer MFIVs shall be OPERABLE.
MODES 1, 2. 3. and 4 except when MFIV is closed and deactivated or isolated by a closed and deactivated power operated valve.
I ACTIONS
NOTE-----------------
Separate Condition entry is allowed for each penetration flow path.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more MFIVs A.1 Close or isolate 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> inoperable.
inoperable MFIV.
AND A.2 Verify inoperable Once per 7 days MFIV is closed or isolated.
B. Two valves in the B.1 Isolate affected flow 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> same flow path path.
AND B.2 Verify inoperable Once per 7 days MFIV is closed or isolated.
(continued)
PALO VERDE UNITS 1,2,3 3.7.3-1 AMENDMENT NO. 117
DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANC;E FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is 2 129 V 7 days on float charge.
SR 3.8.4.2 Verify no visible corrosion at battery 92 days terminals and connectors.
OR Verify battery conrection resistance is
< 150E-6 ohms for inter-cell connections.
< 150E-6 ohms for inter-rack connections.
- 150E-6 ohms for inter-tier connections.
and < 150E-6 ohms for terminal connections.
SR 3.8.4.3 Verify battery cells, cell plates, and 18 months racks show no visual indication of physical damage or abnormal deterioration that could degrade battery performance.
SR 3.8.4.4 Remove visible terminal corrosion and 18 months verify battery cell to cell and terminal connections are clean, and are coated with anti-corrosion material.
SR 3.8.4.5 Verify battery connection resistance is 18 months
< 150E-6 ohms for inter-cell connections.
< 150E-6 ohms for inter-rack connections.
< 150E-6 ohms for inter-tier connections.
and < 150E-6 ohms for terminal connections.
(continued)
I PALO VERDE UNITS 1.2,3 3.8.4-2 AMENDMENT NO. 4;;
DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE I
FREQUENCY SR 3.8.4.8 NOTE--------------------
This Surveillance shall not be performed in MODE 1. 2. 3. or 4.
Verify battery capacity is Ž 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
60 months AND 12 months when battery shows degradation or has reached 85%
of the expected life with capacity
< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity
Ž 100% of manufacturer's rating I
PALO VERDE UNIT 1.2,3 3.8.4-4 AMENDMENT NO. 44%
TABLE 5.5.9-2 STEAM GENERATOR TUBE INSPECTION 1ST SAMPLE INSPECTION 2ND SAMPLE INSPECTION 3RD SAMPLE INSPECTION Sample Size Result Action Required Result Action Required Result Action Required A minimum of C-1 None N.A.
N.A.
N.A.
N.A.
C-1 None N.A.
N.A.
C-2 Plug or repair defective tubes and inspect C-2 Plug or repair C-1 None additional 2S tubes in defective tubes and this S.G.
inspect additional C-2 Plug or repair 4S tubes in this defective tubes
.G.
C-3 Perform action for C-3 result of first sample C-3 Perform action N.A.
N.A.
for C-3 result of first samole C-3 Inspect all tubes in All nthpr SGq Nnnp N.A-N.A.
this b~b., piug or repair C
defective tubes and are -
inspect 2S tubes in each other S.G.
Some S.G.s C-2 Perform action N.A.
N.A.
but no for C-2 result of Notification to NRC additional S.G.
second sample pursuant to 10 CFR 50.72 are C-3 (b)(3)
Additional S.G.
Inspect all tubes N.A.
N.A.
is C-3 in each S.G. and plug or repair defective tubes.
Notification to NRC Dursuant to 10 CFR 50.72 (b)(3)
S = 3- % Where N is the number of steam generators in the unit, and n is the number of steam generators n
inspected during an inspection.
I I
PALO VERDE UNITS 1.2.3 5.5-15 AMENDMENT NO. -124