ML102440121
| ML102440121 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/24/2010 |
| From: | Mims D Arizona Public Service Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 102-06239-DCM/CJS | |
| Download: ML102440121 (7) | |
Text
10 CFR 50.90 Aý A
subsidiaty of Pinnacle West Capital Corporation Dwight C. Mims Mail Station 7605 Palo Verde Nuclear Vice President Tel. 623-393-5403 P. O. Box 52034 Generating Station Regulatory Affairs and Plant Improvement Fax 623-393-6077 Phoenix, Arizona 85072-2034 102-06239-DCM/CJS Auaust 24. 2010 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
References:
- 1. Letter No. 102-06178-DCM/RJR, dated April 29, 2010, From D. C.
Mims, APS to U.S. Nuclear Regulatory Commission, "Request for Amendment to Technical Specification 5.5.8, Inservice Testing Program
- 2. Letter No. 102-06088-DCM/RJR, dated October 30, 2009, from D.C.
Mims, APS, to U.S. Nuclear Regulatory Commission, "Application for Amendment to License Condition C.(1) Maximum Power Level (Units 1 and 3 only), and Various Technical Specifications to Implement Administrative Changes"
Dear Sirs:
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2, and 3 Docket Nos. STN-50-528, 50-529, and 50-530 Supplement to Amendment Requests Associated with Administrative Changes - New Retyped Technical Specification Pages The License Amendments requested in References 1 and 2 contained changes to Technical Specification (TS) pages. The NRC requested that APS provide selected retyped pages.
The retyped pages reflect the correction of typographical errors which do not impact the conclusions of the significant hazards consideration evaluations documented in References 1 and 2. The enclosure to this letter contains the requested retyped TS pages.
No commitments are being made to the NRC by this letter. Should you need further information regarding this submittal, please contact Russell A. Stroud, Licensing Section A member of the STARS (Strategic Teaming and Resource Sharing) Alliance kII Callaway " Comanche Peak
- Diablo Canyon
- Palo Verde 0 San Onofre
- South Texas
- Wolf Creek
, of
ATTN: Document Control Desk U.S. Nuclear Regulatory Commission
Subject:
Administrative Changes - New Retyped TS Pages Page 2 Leader, at (623) 393-5111.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on (Date)
Sincerely, DCM/RAS/CJS/gat
Enclosure:
Retyped Technical Specification Pages cc:
E. E. Collins Jr.
J. R. Hall L. K. Gibson R. I. Treadway A. V. Godwin T. Morales NRC Region IV Regional Administrator NRC NRR Senior Project Manager NRC NRR Project Manager NRC Senior Resident Inspector for PVNGS Arizona Radiation Regulatory Agency Arizona Radiation Regulatory Agency
ENCLOSURE Retyped Technical Specification Pages 3.3.2-5 3.3.5-4 3.4.1-3 5.5-5
RPS Instrumentation Shutdown 3.3.2 Table 3.3.2"1 Reactor Protective System Instrumentation - Shutdown APPLICABLE MODES OR OTHER SPECIFIED SURVEILLANCE.
FUNCTION CONDITIONS REQUIREMENTS ALLOWABLE VALVE
- 1.
Logarithmic Power Level-High(d) 3(a),
4 (a),
5 (a)
- 0.011% NRTP(c)
SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.4 SR 3.3.2.5
- 2.
Steam Generator #1 Pressure-Low(b) 3(a)
SR 3.3.2.21 3990 MWt RTP: Ž 955 psia(')
SR 3.3.2.2 SR 3.3.2.4 SR 3.3.2.5
- 3.
Steam Generator #2 Pressure-Low(b) 3(a)
SR 3.3.2.1 3990 MWt RTP: ý 955 psiaP)
SR 3.3.2i2 SR 3.3.2.4 SR 3.3.2.5 (a)
With any Reactor Trip Circuit Breakers (RTCBs) closed and any control element assembly capable of being withdrawn.
(b)
The setpoint may be decreased as steam pressure is reduced, provided the margin between steam pressure and the setpoint is maintained
- 200 psig.
The setpoint shall be automatically increased to the normal setpoint as steam pressure is increased.
(c)
The setpoint must be reduced to
(d)
-Trip may be bypassed when logarithmic power is > 1E-4% NRTP.
Bypass shall be automatically removed when logarithmic power is :,1E-4% NRTP.
(e)
- 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predetermined as-found acceptance criteria band, then the channel shall.be evaluated to verify that it is functioning as required before returning the channel to service.
If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
- 2. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the UFSAR Trip Setpoint, or within the as left tolerance of.a setpoint that is more conservative than the UFSAR Trip Set Point; otherwise the channel shall be declared inoperable.
The UFSAR Trip Setpoint and the methodology used to determine 1) the UFSAR Trip Setpoint, 2) the predetermined as found acceptance criteria band, and 3) the as-left setpoint tolerance band are specified in the UFSAR.
PALO VERDE UNITS 1,2,3 3.3.2-5 AMENDMENT NO.
ESFAS Instrumentation 3.3.5 Table 3.3!571l(page 1 of 1)
Engineered Safety Features Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED FUNCTION CONDITIONS ALLOWABLE VALUE
- 1. Safety Injection Actuation Signal
- a.
Containment Pressure - High 1,2,3
- 3.2 psig
- b.
Pressurizer Pressure -
Low(a)
> 1821 psia
- 2. Containment Spray Actuation Signal
- a.
Containment Pressure - High High 1,2.3
- 8.9 psig
- 3. Containment Isolation Actuation Signal
- a.
Containment Pressure - High 1,2,3
- 3.2 psig
- b.
Pressurizer Pressure -
Low(a)
Ž 1821 psia
- 4. Main Steam Isolation Signal(c)
- a. Steam Generator #1 Pressure-Low(b) 1,2.3 3990 MWt RTP: Ž 955 psia1
- b. Steam Generator #2 Pressure-Low(b) 3990 MWt RTP: Ž 955 psia")
- c. Steam Generator #1 Level-High
< 91.5%
- d. Steam Generator #2 Level-High
< 91.5%
- e. Containment Pressure-High
! 3.2 psig
- 5. Recirculation Actuation Signal
- a.
Refueling Water Storage Tank Level-Low 1.2.3
> 6.9 and
- 7.9%
- 6. Auxiliary Feedwater Actuation Signal SG #1 (AFAS-1)
- a.
Steam Generator #1 Level-Low 1.2.3
Ž 25.3%
- b.
SG Pressure Difference-High 5 192 psid
- 7. Auxiliary Feedwater Actuation Signal SG #2 (AFAS-2)
- a.
Steam Generator #2 Level-Low 1,2.3
Ž 25.3%
- b.
SG Pressure Difference-High
- 192 psid (a)
The setpoint may be decreased to a minimum value of 100 psia, as pressurizer pressure is reduced, provided the margin between pressurizer pressure and the setpoint is maintained
- 400 psia or Ž 140 psia greater than the saturation pressure of the RCS cold leg when the RCS cold leg temperature is
Ž 485°F.
Trips may be bypassed when pressurizer pressure is < 400 psia.
Bypass shall be automatically removed when pressurizer pressure is Ž 500 psia.
The setpoint shall be automatically increased to the normal setpoint as pressurizer pressure is increased.
(b)
The setpoint may be decreased as steam pressure is reduced, provided the margin between steam pressure and the setpoint is maintained ! 200 psig.
The setpoint shall be automatically increased to the normal setpoint as steam pressure is increased.
(c)
The Main Steam Isolation Signal (MSIS) Function (Steam Generator Pressure - Low, Steam Generator Level-High and Containment Pressure - High signals) is not required to be OPERABLE when all associated valves isolated by the MSIS Function are closed.
(d)
- 1. If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predetermined as-found acceptance criteria band, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
If the as-found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.
- 2. The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the UFSAR Trip Setpoint, or within the as left tolerance of a setpoint that is more conservative than the UFSAR Trip Set Point; otherwise the channel shall be declared inoperable.
The UFSAR Trip Setpoint and the methodology used to determine 1) the UFSAR Trip Setpoint, 2) the predetermined as found acceptance criteria band, and 3) the as-left setpoint tolerance band are specified in the UFSAR.
PALO VERDE UNITS 1,2,3 3.3.5-4 AMENDMENT NO. 4-5;,
RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 Figure 3.4.1-1 Reactor Coolant Cold Leg Temperature vs. Core Power Level iL 0
-JF 575 (C
570 565 560 555 550 545 540 575 570 565 560 555 550 545 540 100 0
I I
I I
I I
I I
I 10 20 30 40 50 60 70 80 90 CORE POWER LEVEL, % OF RATED THERMAL POWER (3990 MWt)
PALO VERDE UNITS 1,2,3 3.4.1-3 AMENDMENT NO. 4-5;,
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of regulatory position c.4.b of Regulatory Guide 1.14, Revision 0, October 1971.
5.5.8 Inservice Testing Program This program provides controls Class 1, 2, and 3 components.
following:
for inservice testing of ASME Code The program shall include the
- a.
Testing frequencies applicable to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:
ASME OM Code and applicable Addenda terminology for inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years Required Frequencies for performing inservice testing activities At least once per 7 days At least once per 31 days At least once per 92 days At least once At least once At least once per 184 days per 276 days per 366 days At least once per 731 days
- b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and
(continued)
PALO VERDE UNITS 1,2,3 5.5-5 AMENDMENT NO. 472-9