ML110320254
| ML110320254 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 02/01/2011 |
| From: | Hall J Plant Licensing Branch IV |
| To: | Edington R Arizona Public Service Co |
| Hall, J R, NRR/DORL/LPL4, 301-415-4032 | |
| References | |
| TAC MD7917, TAC MD7918, TAC MD7919, TAC ME2842, TAC ME2843, TAC ME2844 | |
| Download: ML110320254 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 1, 2011 Mr. Randall K. Edington Executive Vice President Nuclearl Chief Nuclear Officer Mail Station 7602 Arizona Public Service Company P.O. Box 52034 Phoenix, AZ 85072-2034
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION, UNITS 1,2, AND 3 CORRECTION OF TYPOGRAPHICAL ERRORS IN AMENDMENT NOS. 171 AND 182 (TAC NOS. MD7917, MD7918, AND MD7919; AND ME2842, ME2843 AND ME2844, RESPECTIVELY)
Dear Mr. Edington:
On January 23, 2009 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML090060779), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 171 to Facility Operating License No. NPF-41, Amendment No. 171 to Facility Operating License No. NPF-51, and Amendment No. 171 to Facility Operating License No. NPF-74 for the Palo Verde Nuclear Generating Station (Palo Verde), Units 1, 2, and 3, respectively. The amendments consisted of changes to the facility operating licenses and the Technical Specifications (TSs) in response to your application dated January 17, 2008, as supplemented by letter dated February 28, 2008.
Amendment No. 171 added a new license condition on the control room envelope (CRE) habitability program, revised TS 3.7.11 requirements regarding CRE habitability, and established a CRE habitability program in TS 5.5. The new license condition was specified in Appendix D - Additional Conditions, for the three operating licenses. Appendix D had been deleted in a previous amendment, but was restored in Amendment No. 171.
Page 8 of Facility Operating License No. NPF-41, page 8 of Facility Operating License No. NPF-51, and page 6 of Facility Operating License No. NPF-74 were not revised to indicate that Appendix D was no longer deleted. This editorial error only affected the specified pages of the facility licenses and does not change the NRC staff's conclusions regarding Amendment No. 171 for all three Palo Verde units. Enclosed are corrected versions of pages 8,8, and 6 for Facility Operating License Nos. NPF-41, NPF-51, and NPF-74, respectively. Please discard the corresponding license pages and replace them with the enclosed corrected pages for Amendment No. 171.
On November 24,2010 (ADAMS Accession No. ML102710312), the NRC issued Amendment No. 182 to Facility Operating License No. NPF-41, Amendment No. 182 to Facility Operating License No. NPF-51, and Amendment No. 182 to Facility Operating License No. NPF-74 for Palo Verde, Units 1, 2, and 3, respectively. The amendments consisted of changes to the facility TSs in response to your application dated November 30,2009, as supplemented by letter dated July 22, 2010.
R. Edington
- 2 Amendment No. 182 revised TS 3.3.5 requirements regarding refueling water tank (RWT) low level allowable values for the recirculation actuation signal, and TS 3.5.5 requirements for minimum RWT volume. The amendment also approved a revised safety analysis for implementing a time-critical operator action to close the RWT isolation valves for certain accident scenarios.
In the process of issuing the revised pages for Amendment No. 182, we inadvertently introduced a minor editorial error on page 3.3.5-4. We omitted the term "TS" in the heading at the top of the page, which should have read, "Pre-RWT TS Setpoint Change." This editorial error only affected the specified page of the facility TSs and does not change the NRC staff's conclusions regarding Amendment No. 182 for all three Palo Verde units. Enclosed is a corrected version of page 3.3.5-4 for Facility Operating License No. NPF-41, Facility Operating License No. NPF-51, and Facility Operating License No. NPF-74, respectively. Please discard the corresponding TS page and replace it with the enclosed corrected page for Amendment No. 182.
Sincerely,
~/,7m a ~s R. Hall, Senior Project Manager ant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
~
Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosure:
Revised pages for Amendment Nos. 171 and 182 cc w/encl: Distribution via Listserv
ENCLOSURE REVISED PAGES FOR AMENDMENT NOS. NOS. 171, 171, AND 171 AND AMENDMENT NOS. 182,182, AND 182 FACILITY OPERATING LICENSE NOS. NPFA1, NPF-51, AND NPF-74 DOCKET NOS. STN 50-528, STN 50-529, AND STN 50-530 Replace the following pages of the Facility Operating Licenses Nos. NPF-41, NPF-51, and NPF-74, and Appendix A - Technical Specifications, with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Amendment No. 171 Facility Operating License No. NPF-41 REMOVE INSERT -8 Facility Operating License No. NPF-51 REMOVE INSERT -8 Facility Operating License No. NPF-74 REMOVE INSERT -6 Amendment No. 182 Appendix A - Technical Specifications REMOVE INSERT 3.3.5-4 3.3.5-4
- 8 H.
This license is effective as of the date of issuance and shall expire at midnight on June 01, 2025.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosures:
- 1. Attachment 1 - [Requirements for Initial Mode 1 Entry] - Deleted
- 2. Attachment 2 - [Operating Staff Experience Requirements] - Deleted
- 3. Attachment 3 - [Emergency Response Capabilities] - Deleted
- 4. Appendix A-Technical Specifications
- 5. Appendix B Environmental Protection Plan
- 6. Appendix C-Antitrust Conditions
- 7. Appendix D - Additional Conditions Date of Issuance: June 1! 1985 Amendment No. 44+ 171
-8 E.
The licensees shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "Palo Verde Nuclear Station Security Plan, Training and Qualification Plan, Safeguards Contingency Plan and Independent Spent Fuel Storage Installation Security Program Revision 3," submitted by letter dated May 16, 2006.
F.
Deleted G.
The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims; and H.
This license is effective as of the date of issuance and shall expire at midnight on April 24, 2026.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By Darrell G. Eisenhut, Acting Director Office of Nuclear Reactor Regulation Attachments:
- 1. [Requirements for Initial Mode 1 Entry] - Deleted
- 2. [Schedule for NUREG-0737, Sup. 1, Requirement (SPDS)] - Deleted
- 3. Appendix A Technical Specifications
- 4. Appendix B Environmental Protection Plan
- 5. Appendix C Antitrust Conditions
- 6. Appendix D - Additional Conditions Date of Issuance: April 24, 1986 Amendment No. ~ 171
-6 H.
The licensees shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims; and I.
This license is effective as of the date of issuance and shall expire at midnight on November 25,2027.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By Thomas E. Murley. Director Office of Nuclear Reactor Regulation Attachments:
- 1. [Requirements for Initial Mode 1 Entry] - Deleted
- 2. Appendix A Technical Specifications
- 3. Appendix B Environmental Protection Plan
- 4. Appendix C Antitrust Conditions
- 5. Appendix D - Additional Conditions Date of Issuance: November 25, 1987 Amendment No. 4e8 171
3.3.5 Pre*RWT TS Setpoint Change ESFAS Instrumentation Table 3,3,5-1 (pa~e 1 of 1)
Engineered Safety Features Actuatlon System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED FUNCTION CONDITIONS ALLI)1ABL E VALUE
- 1. Safety InJection ktuation Slgnal
- a.
- b.
Conta1nment Pressure - High Pressuri zer Pressure - Low( aJ
- 1. 2.3
- s; 3.2 psig 2: 1821 PS1 a 2 Containment Spray Actuation Signal
- a.
Containment Pressure - High High 1.2.3 s 8.9 psig
- 3. Conta1nment Isolation Actuation Signal
- a.
- b.
Containment Pressure Pressuflzer Pressure - H1gh
- Low(a) 1.2.3 s: 3.2 pS1g
<: 182: psia
- 4. Main Steam Isolation Signal(c)
- a.
Steam Generator #1 Pressure-Low(b) 1.2,3 3990 MWt RTP:
~ 955 psialQl D.
Steam Generator #2 Pressure-LoweD) 3990 MWt RTP: <: 955 psi aid)
- c.
- d.
- e.
Steam Generator #1 Level-High Steam Generator #2 Level-High Containment Pressure-High s: 91.5%
- > 91.5%
- or; 3.2 psig
- 5. Recirculation Actuation Signal
- d.
Refuel ing Water Storage Tank Level-Low 1.2.3
<: 6.9 and 5 7 9;
- a.
- b.
Steam Generator #1 Leve'-Low SG Pressure Oifference-High 1.2.3
~ 25.3%
., 192 psid Aux1l1ary Feedwater Actuation Slgna: SG #2 (AFAS-2) a,
- b.
Steam Generator #2 Level-LOW SG Pressure Difference-High 1.2,3
<: 25.3%
s 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 ~ 140 psia greater than the saturation pressure of the RCS cold leg when the RCS cold leg temperature is 2: 485 Q F.
Trips may be bypassed when pressurizer pressure is < 400 psia. Bypass shall be automatically removed when pressurizer pressure is 2: 500 psia. The setpo1nt shall be automatically 1ncreased to the normal setpoint as pressurizer pressure is increased.
(b)
The setpoint may be decreased as steam pressure's reduced. proviCec the margin between stean pressure and the setpoint is maintainecs: 200 psig.
The setpoint Shall be automatically increased to the normal setpoint as steam pressure 15 lncreasec.
(c)
The Main Steam Isolat1on Signal (MSIS) Function (Steam Generator Pressure - Low. Steam Generator Level f-ligh and Contdlnment Pressure f'-.gh signals) is not requlrec to be OPERABLE when al1 aSSOCiated valves isolated by the MSIS Function are closee, (d)
I. If the as-found channel setpoint is conservative w1th respect to the Allowable Value but outs1de its predetermlnec as-found acceptance crlteria band. then the channel shall be evaluated to verl fy that 1t is functlonlng as requ1rec 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 i noperab1e.
- 2. The instrument channel setpo'nt shall be reset to a value that is wlthin the as-left tolerance of the UFSAR Trlp Setpoint. or w,tnin the as left tolerance of a setpoint that 'lS more conservative than the UFSAR Trlp Set POint; otherwise the channel shall De ceclared inoperable.
The UFSAR Trip Setpoint and the methodology used to determ1ne 1) the UFSAR Trip Setpoint. 2) the predetermined as found acceptance criteria Dand. and 3) the as-left setpoint tolerance nand are specified in the UFSAR PALO VERDE UNITS 1.2.3 3.3.5-4 AMENDMENT NO. ~. 182
R. Edington
- 2 Amendment No. 182 revised TS 3.3.5 requirements regarding refueling water tank (RWT) low level allowable values for the recirculation actuation signal, and TS 3.5.5 requirements for minimum RWT volume. The amendment also approved a revised safety analysis for implementing a time-critical operator action to close the RWT isolation valves for certain accident scenarios.
In the process of issuing the revised pages for Amendment No. 182, we inadvertently introduced a minor editorial error on page 3.3.5-4. We omitted the term "TS" in the heading at the top of the page, which should have read, "Pre-RWT TS Setpoint Change." This editorial error only affected the specified page of the facility TSs and does not change the NRC staffs conclusions regarding Amendment No. 182 for all three Palo Verde units. Enclosed is a corrected version of page 3.3.5-4 for Facility Operating License No. NPF-41, Facility Operating License No. NPF-51, and Facility Operating License No. NPF-74, respectively. Please discard the corresponding TS page and replace it with the enclosed corrected page for Amendment No. 182.
Sincerely, Ira!
James R. Hall, Senior Project Manager Plant licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-528, STN 50-529, and STN 50-530
Enclosure:
Revised pages for Amendment Nos. 171 and 182 cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPLIV rlf RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMPaloVerde Resource ADAMS Accession No. ML110320254 RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource RecordsAmend Resource OFFICE NRR/LPL4/PM NRRlLPL4/LA NRR/LPL4/BC NRRlLPL4/PM II NAME JRHall JBurkhardt MMarkley JRHali DATE 2/1/11 2/1/11 2/1/11 2/1/11 OFFICIAL AGENCY RECORD