ML20237B055
| ML20237B055 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/30/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-0857, NUREG-0857-S12, NUREG-857, NUREG-857-S12, NUDOCS 8712150439 | |
| Download: ML20237B055 (27) | |
Text
,, , . . - .
- NUREG-0857 l Supplement No.12 Safety Evaluation Report I
relatec to the operation of Palo Verde \uclear Generating Station, Units 1,2, and 3 Docket Nos. STN 50-528, STN 50-529, and STN 50-530 Arizona Public Service Cornpany, et al.
U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation November 1987 pc arco,
+ #g 1
)[] K ) lb z ona
- r NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources:
i
- 1. The NRC Public Document Room,1717 H Street, N.W.
Washington, DC 20555
- 2. The Superintendent of Documents, U.S. Government Printing Office, Post Office Box 37082, Washington, DC 20013 7082
- 3. The National Technical Information Service, Springfield, VA 22161 Although the listing that follows represents the majority of documents cited in NRC publications, ,
it is not intended t:De exhaustive.
Referenced documents available for inspection and copying for a fee from the NRC Public Docu-ment Room include NRC correspondence and internal NRC memoranda; NRC Office of Inspection and Enforcement bulletins, circulars, information notices, inspection and investigation notices; Liccosee Event Reports; vendor reports and correspondence; Commission papers; and applicant and licensee documents and correspondence.
The following documents in the NUREG series are available for purchase from the GPO Sales Program: formal NRC staff and contractor reports, NRC-sponsored conference proceedings, and NRC booklets and brochures. Also available are Regulatory Guides, NRC regulations in the Code of Federal Regulations, and Nuclear Regulatory Commission issuances.
Documents available from the National Technical information Service include NUREG series reports and technical reports prepared by other federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.
Documents available from public and special technical libraries include all open literature items, such as books, journal and periodical articles, and transactions. Federal Register notices, federal and state legislation, and congressional reports can usually be obtained from these libraries.
Documents such as theses, dissertations, foreign reports and translations, and non-NRC conference proceedings are available for purchase from the organization sponsoring the publication cited.
Single copies of NRC draf t reports ace available free, to the extent of supply, upon written request to the Division of information Support Services, Distribution Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555.
Copies of mdustry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, and are available there for reference use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards institute,1430 Broadway, New York, NY 10018.
NUREG-0857 Supplement No.12 .
Safety Evaluation Report .
related to the operation of -
Palo Verde Nuclear Generating Station, .
Units 1, 2, and 3 Docket Nos. STN 50-528, STN 50-529, and STN 50-530 Arizona Public Service Company, et al.
U.S. Nuclear Regulatory Commission Office of Nuclear > r Regulation November 1987 s p =%,,
t, f s
ABSTRACT Supplement No. 12 to the Safety Evaluation Report for the application filed by Arizona Public Service Company et al. for licenses to operate the Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Docket Nos. STN 50-528/529/530),
located in Maricopa County, Arizona, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. The purpose of this supplement is to update the Safety Evaluation Report by providing an evaluation of (1) additional information submitted by the applicant since Supplement No. 11 was issued and (2) other matters requiring staff review since Supplement No. 11 was issued, specifically those issues that required resolution before Unit 3 full power licensing.
l l
l Palo Verde SSER 12 iii
TABLE OF CONTENTS Page ABSTRACT .. ........... ......... .... ............. ................. iii ,,
1 INTRODUCTION AND GENERAL DISCUSSION ......... .. . . . ........... 1-1 -
1.1 Introduction ..... . ........ .... ... ...................... 1-1 1.9 Summary of Outstanding Issues ... ... . ..... . ......... 1-2 1.11 License Conditions ........ ......... ................ . 1-2 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS ... ................. 5-1 -
5.4 Component and Subsystem Design ........ ...... ............... 5-1 L 5.4.1 Reactor Coolant Pumps . ........ ...................... 5-1 APPENDIX A CONTINUATION OF CHRON0 LOGY OF RADIOLOGICAL REVIEW APPENDIX E ABBREVIATIONS D,
. L Palo Verde SSER 12 v
l 1 INTRODUCTION AND GENERAL DISCUSSION 1.1 Introduction On November 13, 1981, the Nuclear Regulatory Commission (NRC) staff issued its Safety Evaluation Report (SER) relating to the application for licenses to oper-ate the Palo Verde Nuclear Generating Station, Unit Nos. 1, 2, and 3 (PVNGS 1-3);
Supplement Nos. 1 through 11 to the SF.R were issued on February 4, 1982; May 17, 1982; September 23, 1982; March 15, 1983; November 28, 1983; October 31, 1984; December 31, 1984; June 1, 1985; December 9, 1985, April 24, 1986, and March 25, 1987, respectively. The application was submitted by the Arizona Public Ser-vice Company (APS or the applicant *) on behalf of itself, the Salt River Proj-ect Agricultural Improvement and Power District, Southern California Edison Company, El Paso Electric Company, Public Service Company of New Mexico, Los Angeles Department of Water and Power, and Southern California Public Power Authority. An operating license (NPF-34) restricted to 5% of full power was issued for Unit 1 on December 31, 1984, and a full power operating license (NPF-41) was issued on June 1, 1985. An operating license (NPF-46) restricted to 5% of full power was issued for Unit 2 on December 9, 1985, and a full power operating license (NPF-51) was issued on April 24, 1986. An operating license (NPF-65) restricted to 5% of full power for Unit 3 was issued on March 25, 1987.
In the SER and its supplements, the staff identified certain issues concerning Units 2 and 3 for which either further information was required of the applicant or additional staff effort was needed to complete the review. The purpose of this supplement is to update the SER by providing an evaluation of (1) addi-tional information submitted by the applicant since Supplement No. 11 to the SER was issued and (2) other matters requiring staff review since Supplement No. 11 was issued.
Each of the following sections of this supplement is numbered the same as the section of the SER (and its supplements) that is being updated and, unless otherwise noted, the discussions are supplementary to and not in lieu of the previous discussions. Appendix A to this supplement is a continuation of the chronology. Appendix E is a list of abbreviations used in this supplement.
All other appendices to the SER and its supplements are not changed by this twelfth supplement.
M. Davis, the Project Manager for Palo Verde, is the principal contributor to this supplement.
However, throughout this SSER, APS is referred to as the applicant.
Palo Verde SSER 12 1- 1
f 1.9 Summary of Outstanding Issues Since Supplement 11 was issued, new issues arose that required the staff's eval-uation. One issue is identified below; the section of this supplement in which this issue is evaluated is given in parentheses.
(1) reactor coolant pumps (Section 5) 1.11 License Conditions The following conditions have been added to the Unit 3 full power license:
(1) Reactor coolant pump shaft vibration monitoring (see Section 5.4.1)
(2) Requirement to modify reactor coolant pump shaf ts during first refueling outage (see Section 5.4.1)
(3) Requirement to submit a report to NRC concerning the inspection of the Unit 2 reactor coolant pump shafts (see Section 5.4.1) l Palo Verde SSER 12 1-2
\
l 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS l 5.4 Component and Subsystem Design 5.4.1 Reactor Coolant Pumps Shaft Cracking Experience By letter dated October 8, 1987, the applicant informed the Commission that European reactor coolant pumps similar to the Palo Verde pumps in design and manufacture had cracks in their shafts. Cracks have been found in 21 of 27 European shafts after 22,500 to 64,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of operation and two shafts had failed. The actual failures occurred after 47,500 and 41,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of pump operation. As a result, the applicant informed the Commission that it planned to inspect the shafts of the pumps at Palo Verde Unit 1 during the current re-fueling outage, October-December 1987. In the applicant's letter of October 21, 1987, it reported that the inspection began on October 14, 1987. Upon comple-tion of an ultrasonic inspection of the shaft of the first two pumps, cracks of varying depths and lengths had been identified. Subsequently, cracks were detected in the two remaining pumps. No shaft failures have been experienced at Palo Verde.
The applicant met with the Commission staff on October 24, 1987, to review the history of pump shaft cracking in Europe, the findings at Palo Verde Unit 1, and to propose actions to be taken with respect to operation of Palo Verde Units 1, 2, and 3.
After the meeting on October 25, 1987, the Commission issued an immediately effective order confirming applicant commitments on monitoring vibration of RCP shafts at Palo Verde Unit 2 which requires the following:
(1) Every four hours, monitor and record the vibration data on each of the four reactor coolant pumps.
(2) On a daily basis, have an appropriately qualified engineer evaluate the pump vibration data obtained in item 1 above.
(3) When any one vibration monitor on the reactor coolant pumps indicates a vibration level of 8 mils or greater, the Nuclear Regulatory Commission shall be notified within four hours via the Emergency Notification System.
(4) When any one vibration monitor on the reactor coolant pumps indicates a vibration level of 10 mils or greater, within one hour, initiate action to place the unit in at least hot standby within the next six hours, and at least cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
After the meeting, teams from Arizona Public Service Company (APS) and the NRC traveled to Germany to investigate European experience with the cracking of Palo Verde SSER 12 5-1
reactor coolant pump (RCP) shafts. Another meeting was held on November 4, 1987 to review information gathered in Europe and to review actions taken on the Palo Verde units.
As a result of the trip to Germany, the applicant provided the following infor-mation concerning European experience with RCP shaft cracking.
In the two European shaft failure events, shutdowns were uncomplicated and no failed fuel resulted. One of the plants continued to operate at reduced power for a month after the event. The analysis of a single shaft failure for Palo Verde with realistic assumptions as compared to conservative regulatory assump-tions shows, as expected, no fuel failure. The analysis shows lcwer combined stresses on the unaffected pumps following the single failed shaft event.
Therefore, one shaft failure should not result in an increased probability that another shaft would fail.
Experience with monitoring vibration amplitude from plants that have experi-enced failed shafts indicates that vibration monitoring should provide indica-tion of impending shaft failure at least 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> before the event. Advanced vibration monitoring techniques such as spectrum analysis to determine fre-quency shifts could provide earlier warning of serious shaft defects.
European metallurgical and fractographic evaluations indicate that fatigue cracking initiates in the chrome plating as a result of normal operating and thermal stresses. The microcracks developed in the chrome plating then act as stress raisers to initiate cracks in the base metal. The cracks in the base metal then propagate by high cycle fatigue.
Inspections of Palo Verde Unit 1 RCP shafts revealed indications of cracking near the top of the keyway with operating times between 17,500 and 19,400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />. The Palo Verde experience is generally consistent with the European experience.
Shaft Modification After the European trip, the applicant presented its findings with respect to continued operation of Units 2 and 3 at a meeting on November 4,1987, The Palo Verde Unit 1 RCP shafts are being replaced with modified spare shafts.
The modifications consist of (1) removal of the chrome plating in all moderate to high stress areas where cracking has been experienced, (2) extending the stop seal to prevent thermal shock of direct seal water impingement on the shaft, and (3) shortening of the key to clear the new extended stop seal.
European inspections of modified shafts have found no cracking after 6,500 to 15,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of pump run time. The Unit 2 and Unit 3 shafts will be removed for modification during the first refueling outages (early 1988 for Unit 2 and early 1989 for Unit 3). After the Unit 2 shafts are inspected, an analysis of the results and recommendations concerning continued operation of Unit 3 are to be submitted to the staff.
Palo Verde SSER 12 5-2
Vibration Monitoring The vibratio, monitoring systems at Palo Verde Units 1, 2, and 3 include motor accelerometers and X-Y proximity probes. A third transducer probe for measuring phase angle has been installed in Unit 3 RCPs, is to be installed in Unit 1 RCPs during the current outage, and is scheduled to be installed in Unit 2 during the first refueling outage (planned for February 1988). Advanced sys-tems for vibration monitoring have been installed in Units 2 and 3 for evaluation.
As a result of the discussions in Europe and at the November 4, 1987 meeting, the staff concluded that the effectiveness of the vibration monitoring program described in the October 25, 1987 Confirmatory Order should be enhanced by including a spectral analysis of the vibration data to provide earlier warning trends if a crack has started and is propagating. In letters dated November 5 and 12, 1987, the applicant has committed to further augment the reactor cooling pump monitoring program by including a spectral analysis of the data.
The Commission subsequently issued a modification to the Unit 2 Confirmatory Order of October 25, 1987 (see page 5-1) requiring the applicant to implement an augmented vibration monitoring program for each of the four reactor coolant pumps that includes the following elements:
(1) Every four hours, monitor and record the vibration data on each of the four reactor coolant pumps.
(2) On a daily basis, have an appropriately qualiiied engineer evaluate the pump vibration data obtained in item 1 above.
(3) When any one vibration monitor on the reactor coolant pumps indicates a vibration level of 8 mils or greater, the Nuclear Regulatory Commission shall be notified within four hours via the Emergency Notification System.
In addition, when the vibration on any pump exceeds 8 mils because of a shaft crack or unknown cause, within four hours the affected pump shall have its orbit and spectra continuously monitored and evaluated by an appropriately qualified individual.
(4) When any one vibration monitor on the reactor coolant pumps indicates a vibration level of 10 mils or greater, within one hour, initiate action to place the unit in at least hot standby within the next six hours, and at least cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. In addition the affected pump shall be secured after entering hot standby (Mode 3).
(5) On a daily basis, a spectrum analysis shall be performed on the reactor coolant punip shaf t vibration data and shall be evaluated for trends by an individual qualified in that technique. The evaluation shall consist of comparing the running speed (1xRPM) and twice running speed (2xRPM) spec-tral components to limits computed from the baseline vibration. The limits shall be based on the lowest of: (a) 1.6 times the baseline value; (b) the mean plus three standard deviations; (c) 2 mils for the 2xRPM component; or (d) 6 mils for the 1xRPM component. When the amplitude exceeds any limit, further analysis shall be performed. This analysis shall consist of an inspection of the amplitude versus time plots for a
steadily increasing trend, and a review of other plant data that might explain the change in amplitude. If it is confirmed that the trend is not caused by plant or pump conditions unrelated to a shaft crack, the trend shall be extrapolated manually and/or by computer to piedict the time at which the vibration is expected to reach 10 mils. If the projected time for reaching 10 mils is one week or less, the unit shall be brought to hot standby pursuant to item 4 above and the affected pump shall be secured.
After reaching hot standby, the unit shall proceed to cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
The modification also required that the applicant install modified reactor coolant pump shafts during the next refueling outage currently scheduled to start in February 1988. These pump shafts should inc~lude the modifications described in Figure DES-3 of the attachments to the applicant's November 5, 1987 letter.
Conclusion Each unit at Palo Verde has an effective vibration monitoring program in place.
Such monitoring programs will detect the occurrence of severe cracking on the pump shafts a week before the actual failure, which is adequate to provide timely warning for an orderly plant shutdown.
Key points from an operational history comparison of the three Palo Verde units are:
(1) Total projected pump operating hours for Unit 2 at refueling (-15,800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />) will be approximately 20% less than the actual Unit 1 pump hours (19,400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />).
(2) The Unit 2 pumps will have approximately 25% fewer starts and stops than the Unit 1 RCPs.
(3) The Unit 2 pump operating hours at low temperatures (higher shaft stress) are on average 50% less than Unit 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
(4) The loss-of-seal-injection events for Unit 2 pumps (2 occurrences) are less than the Unit 1 1B pump (13 occurrences).
(5) The operating history of Unit 3 should be similar to that of Unit 2.
For these reasons, the Unit 2 and Unit 3 RCP shafts could be expected to experience a lesser degree of shaft crack indications than the Unit 1 shafts.
For these reasons and because adequate shaft vibration monitoring capability and procedures are in place, the staff concludes that Unit 2 and Unit 3 can complete their first cycle of operation without undue risk to the public health and safety. For Unit 3, the staff will assess the results of the Unit 2 in-spection and the accompanying analysis after the 1988 Unit 2 refueling outage to determine if there is need for revising the staff position on Unit 3.
Palo Verde SSER 12 5-4
APPENDIX A CONTINUATION OF CHRONOLOGY OF RADIOLOGICAL REVIEW March 20, 1987 Letter from applicant concerning corrective actions for inadvertent main steam isolation valve opening and Unit 2 inverter problems.
March 20, 1987 Letter from Region V to applicant transmitting Federal Emergency Management Agency memo and report on emergency exercise.
March 23, 1987 Letter to applicant forwarding request for additional information regarding response to NUREG-0737, Item II.D.1, concerning performance testing of relief and safety valves.
March 23, 1987 Letter from applicant forwarding emergency technical specification change request concerning secondary system liquid waste discharges to onsite evaporation ponds at Unit 1.
March 24, 1987 Letter from applicant transmitting recovery program for emergency diesel generator engine at Unit 3.
March 25, 1987 Issuance of Facility Operating License No. NPF-65 authorizing fuel loading and operation of Unit 3 up to 5%
of power and issuance of Supplement No. 11 to the Safety Evaluation Report.
March 27, 1987 Letter from applicant concerning operator and senior operator license renewals.
March 27, 1987 Letter from applicant forwarding additional information on emergency operating procedures, in response to NRC letter of September 10, 1986.
March 27, 1987 Letter from applicant transmitting revised response to Generic Letter 85-02.
March 28, 1987 Letter to applicant transmitting request for additional information regarding American Society of Mechanical Engineers Code Section XI, pump and valve inservice testing program.
March 28, 1987 Letter from applicant providing certification of the operability of all required systems for initial fuel load of Unit 3.
Palo Verde SSER 12 1 Appendix A
March 30, 1987 Letter from applicant regarding proposed inoperability of both control element assembly calculators while performing certain surveillance tests.
March 30, 1987 Letter to applicant transmitting listing of revisions of approved physical security, safeguards contingency, and guard training and qualification plans for Unit 3.
March 30, 1987 Letter from applicant's attorney regarding sale and lease-back transaction by Public Service Company of New Mexico (PNM).
April 1, 1987 Letter to applicant forwarding request for additional information concerning application for change to the technical specification regarding shutdown margin.
April 3, 1987 Letter from applicant's attorney regarding sale and lease-back transaction by PNM.
April 6, 1987 Letter from applicant forwarding proposed technical specification changes regarding surveillance require-ments for pressurizer heater capacity.
April 7, 1987 Letter to applicant regarding reactor coolant pump (RCP) coastdown safety analysis.
April 8, 1987 Issuance of Amendment 14 to Facility Operating License NPF-41 and Amendment 8 to Facility Operating License NPF-51 concerning technical specification changes to the fire protection program.
April 8, 1987 Issuance of Amendment 15 to Facility Operating License NPF-41 and Amendment 9 to Facility Operating License NPF-51 Technical Specification changes to remove main steam iso-lation valves from list of valves subject to requirements of specifications.
April 9, 1987 Letter from applicant providing certification of oper-ability of all required systems for initial fuel load of Unit 3.
April 16, 1987 Letter from applicant providing comments on reactor operator and senior reactor operator examinations.
April 22, 1987 Meeting with applicant to discuss Cycle 2 core reloads for Units 1 and 2.
April 22, 1987 Letter from applicant providing additional ccmments on reactor operator and senior reactor operator examinations administered on April 10, 1987.
Palo Verde SSER 12 2 Appendix A
l April 23, 1987 Letter from applicant providing revised information to proposed technical specification changes on boration requirements submitted on January 23, 1987.
April 24, 1987 Issuance of Sholly notice regarding pressurizer heaters.
April 24, 1987 Issuance of Sholly notice regarding surveillance require-ments for the hydrogen recombiner power control cabinets of Unit 3.
April 24, 1987 Letter from applicant concerning postaccident sampling system.
April 28, 1987 Letter to applicant forwarding evaluation of recovery pro-gram for emergency diesel generator B of Unit 3.
April 29,1987 Issuance of Amendment 16 to Facility Operating License NPF-41 regarding technical specification change, on a one-time basis for period not to exceed 60 days, authorizing release of secondary system liquid waste to the onsite evaporation pond (emergency authorization confirmed by telephone March 24, 1987).
April 30, 1987 Letter from applicant regarding RCP coastdown safety analysis.
May 4, 1987 Letter from applicant transmitting proposed technical specification change concerning variable overpower trip function.
May 4, 1987 Letter to applicant advising of acceptability of and trans-mitting safety evaluations for its response to Generic Letter 83-28, Items 4.2.1-4.2.4.
May 5, 1987 Letter to applicant forwarding detailed evaluation of SPDS.
May 6, 1987 Letter from applicant transmitting proposed technical specification change regarding limiting condition for operation and surveillance requirements.
May 8, 1987 Meeting with applicant to discuss revised shutdown margin requirements and variable overpower trip setpoints.
May 10, 1987 Letter from applicant forwarding request for emergency technical specification change to extend time period for release of secondary system liquid waste discharges to onsite evaporation pond to March 31, 1988.
May 11, 1987 Letter from applicant transmitting proposed technical specification change regarding applicability for manual setpoint adjustments, a mode change at Unit 1.
Palo Verde SSER 12 3 Appendix A
May 11, 1987 Generic Letter 87-08, " Implementation of 10 CFR 73.55 Miscellaneous Amendment and Search Requirements."
May 12, 1987 Letter from applicant providing supplemental information regarding proposed technical specification change on onsite evaporation ponds at Unit 1.
May 12, 1987 Letter to applicant requesting additional information for May 10 request for technical specification change on onsite evaporation ponds.
May 14, 1987 Issuance of individual Sholly notice related to May 10 application on onsite evaporation pond at Unit 1.
May 15, 1987 Letter from applicant transmitting additional information related to proposed technical specification change on hydrogen recombiners.
May 15, 1987 Letter from applicant forwarding " Modified Statistical Combination of Uncertainties" (proprietary).
May 16, 1987 Letter to applicant advising that the May 10 request for emergency technical specification change will be handled expeditiously, but not as an emergency. Also transmitting copy of related notice sent to Federal Register.
May 18, 1987 Letter from applicant transmitting FSAR Amendment 17.
May 20, 1987 Issuance of bi-weekly Sholly notice regarding reactor protection instrumentation trip setpoint limits / variable overpower trip.
May 25, 1987 Letter from applicant forwarding application for license amendment to eliminate typos, provide additional clarifica-tion, improve consistency, and make other administrative changes for Unit 1.
May 25, 1987 Letter from applicant transmitting proposed change to FSAR concerning QA program at Unit 1.
May 27, 1987 Letter to applicant regarding unescorted site access for M. Davis.
May 27-28, 1987 Meeting with applicant regarding inservice testing program for pumps and valves.
May 28, 1987 Letter from applicant transmitting proposed technical specification changes on incore detector instrumentation and boration at Unit 1.
May 29, 1987 Letter from applicant forwarding report of a security event at Unit 1.
Palo Verde SSER 12 4 Appendix A
May 29, 1987 Letter from applicant advising of clarification of meeting summary concerning positive moderate temperature coefficient at Unit 1.
May 29, 1987 Letter to applicant transmitting request for additional information regarding onsite evaporation ponds.
June 1, 1987 Letter from applicant transmitting 10 CFR 50.59 Annual Report for the 1986 Calendar Year.
June 1, 1987 Letter to applicant transmitting IE Information Notice 86-98, "Offsite Medical Services."
June 3, 1987 Issuance of Amendment 17 to Facility Operating License NPF-41 for technical specification changes regarding pressure values for testing containment leakage rates and containment air lock door.
June 3, 1987 Issuance of Amendment 18 to Facility Operating License NPF-41 for technical specification change concerning release of secondary system liquid waste to the onsite evaporation pond until March 31, 1988.
June 4, 1987 Generic Letter 87-09, " Applicability of Limiting Conditions for Operation and Surveillance Requirements."
June 8, 1987 Letter from applicant providing information regarding temperature-dependent shutdown margin.
June 8, 1987 Letter from applicant forwarding slide package from April 22 meeting (proprietary).
June 11, 1987 Letter from applicant providing response to Generic Letter 87-06, " Periodic Verification of Leak Tight Integrity of Pressure Isolation Valves."
June 12, 1987 Letter from applicant advising that response to request for additional information regarding onsite evaporation ponds will be submitted by July 31,.1987.
June 12, 1987 Generic Letter 87-10, " Implementation of 10 CFR 73.5'7 Requirements for FBI Criminal History Checks."
June 18, 1987 Letter from applicant transmitting Supplement 2 to startup report for Unit 2 and forwarding information on reactor coolant and secondary chemistry and radiochemistry.
June 19, 1987 Generic Letter 87-11, " Relaxation in Arbitrary Intermediate Pipe Rupture Requirements."
June 22, 1987 Letter from applicant forwarding information on reactor coolant pump coastdown safety analysis.
June 22, 1987 Letter from applicant forwarding request for technical specification change concerning Control Element Assembly Symmetry Test Program for Unit 3.
June 22, 1987 Letter from applicant forwarding information in response to telephone conversation concerning Unit 1 Cycle 2 reload technical specifications.
June 24, 1987 Letter from applicant forwarding supplement to piping verifi-cation test summary for Unit 1.
June 24, 1987 Letter from applicant providing response to IE Information Notice 86-98, "Offsite Medical Services."
June 24, 1987 Letter from applicant forwarding proposed technical specifi-cation change concerning condensate storage tank level.
June 28, 1987 Letter from applicant forwarding status report of diesel generator testing et Unit 3.
June 29, 1987 Letter from applicant transmitting Unit 1 Cycle 2 Reload Analysis Report.
June 29, 1987 Letter from applicant transmitting proposed technical specification changes related to Unit 1 Cycle 2 reload.
June 29, 1987 Letter from applicant advising of change to the Initial Test Program for Units 2 and 3.
June 29, 1987 Letter from applicant forwarding special report on steam generator inservice inspection for Unit 1.
July 1, 1987 Issuance of bi-weekly Sholly notice regarding trip setpoints for low pressurizer pressure and low steam generator pres-sure at Unit 1.
July 1, 1987 Letter to applicant transmitting request fcr additional information to complete review of its responses to Generic Letter 83-28, Item 2.1, Part 2 and Item 2.2.
July 1, 1987 Letter from applicant forwarding request for technical specification change containing Control Element Assembly Symmetry Test Program for Units 1 and 2.
July 2, 1987 Letter from applicant concerning change to the FSAR, made in compliance with Regulatory Guide 1.45, regarding gaseous and airborne monitor being used for detection although procedures are in place to use other means for quantifying reactor coolant system leakage.
July 10, 1987 Meeting with applicant to discuss results of 3B emergency diesel generator testing program.
Palo Verde SSER 12 6 Appendix A
July 13,1987 Letter from applicant concerning CPC Software Revision 3 and Loss of Flow Analysis. i July 13, 1987 Letter from applicant providing response to request for aaditional information for proposed reload technical spe-cification amendment.
July 13, 1987 Letter from Combustion Engineering transmitting Palo Verde Steam Generator Tube Vibration Evaluation Program Progress Report.
July 15, 1987 Issuance of bi-weekly Sholly notice regarding condensate storage tank.
July 15, 1987 Issuance of bi-weekly Sholly notke regarding incore detectors.
July 17, 1987 Letter from applicant regarding fire door installation.
July 17, 1987 Letter from applicant regarding proposed technical speci-fication change on boration requirements when in shutdown, by modification of the shutdown margin requirements.
July 22, 1987 Letter to applicant transmitting request for additional information concerning Unit 1 Cycle 2 reload.
July 22, 1987 Letter from applicant advising that response to request for additional information related to Generic Letter 83-29 will be submitted by September 15, 1987.
July 23, 1987 Issuance of bi-weekly Sholly notice regarding boration requirements.
July 23, 1987 Letter from applicant forwarding application for license amendment authorizing sale and leaseback transaction for Unit 3 by El Paso. ,
l 4
July 23, 1987 Letter to applicant forwarding evaluation of operation in j Modes 3, 4, and 5 with less than 4 reactor coolant pumps {
running.
July 24, 1987 Letter from applicant regarding PASS (Unit 1).
July 28, 1987 Letter from applicant concerning sale and leaseback trans-actions on Unit 2 by APS.
July 30, 1987 Letter from applicant transmitting response to request for !
I additional information on Item II.D.1 of NUREG-0737.
Juiy 31, 1987 Letter from applicant forwarding response to request for additional information regarding onsite evaporation ponds.
I Palo Verde SSER 12 7 Appendix A
l August 4, 1987 Generic Letter 87-14. " Operator Licensing Examinations."
August 7, 1987 Letter from applicant providing additional information regarding Unit 1 technical specification change request of May 25, 1987.
August 7, 1987 Letter from applicant advising of its intent to terminate the provisions of Amendment 13 to security plan.
August 7, 1987 Letter from applicant forwarding information concerning the inservice inspection program.
August 7, 1987 Letter from applicant providing clarification regarding its technical specification change request concerning CEA Symmetry Test Program.
August 10, 1987 Letter to applicant requesting additional information re-lated to the Unit 1 piping verification test summary.
August 10, 1987 Issuance of bi-weekly Sholly notice regarding CEA Symme'ry Test Program.
j i
August 10, 1987 Letter from applicant requesting license amendments regard-ing proposed organizational changes.
(
August 12, 1987 Letter from applicant regarding sale and leaseback trans-action by PNM.
August 12, 1987 Meeting with applicant to discuss NRC concerns generated during assessment of the operating performance of Units 1 and 2 in consideration of the pending licensing decision for Unit 3, and to identify needed licensee actions for improvement prior to licensing decision.
August 13, 1937 Issuance of bi-weekly Sholly notice regarding Cycle 2 operation at Unit 1.
August 13, 1987 Issuance of bi-weekly Sholly notice regarding proposed reorganization.
August 14, 1987 Issuance of Amendment No.19 to Facility Operating License No. NPF-41, Amendment No.10 to Facility Operating License No. NPF-51, and Amendment No. 1 to Facility Operating License No. NPF 65 - technical. specification changes regarding (1) a veillance requirements for the hydrogen recombiner sys;.'.n, (2) specified capacity for pressurizer i heaters, (3) definitions of the rate and band inputs to I the variable overpower trip function, and (4) authorization to combine two steps in TS 3.0.3 to achieve hot shutdown from hot standby within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown within subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> into one step for achieving cold shut-
[
down from hot standby within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 1
Palo Verde SSER 12 8 Appendix A
August 20, 1987 Letter from applicant transmitting Fuel Assembly Guide Tube i Wear Program for Unit 2.
August 20, 1987 Letter fror, nplicant providing response to questions re-garding Vait . Cycle 2 reload submittal.
August 20, 1987 Letter from applicant providing revision to proposed reload i technical specification amendment.
l August 24, 1987 Letter from applicant transmitting additional information on Unit 3 diesel generator testing. i August 25, 1987 Letter to applicant advising of acceptability of software changes to CPC.
August 27, 1987 Issuance of Sholly notice concerning proposed enhancement of the Unit 1 technical specifications to make them con-sistent with the technical specifications of Ur.its 2 and 3.
August 31, 1987 Letter from applicant forwarding changes to the Unit 3 Initial Test Program.
August 31, 1987 Letter from applicant transmitting Amendment 15 to security plan.
August 31, 1987 Letter from applicant advising that response to request for information on piping verification test summary will be provided by October 30, 1987.
August 31, 1987 Letter from applicant advising of APS sale and leaseback transactions on Unit 2.
August 31, 1987 Letter from applicant providing information on charging pump blocks.
l August 31, 1987 Letter from applicant forwarding revised Section 1.9.2, l
" Exceptions to CESSAR" of FSAR. l
)
l September 1, 1987 Letter to applicant requesting schedule and identification i of activities planned during Unit 1 refueling.
l l S ptember 1, 1987 Letter to applicant transmitting NUREG-1275, " Operating l Experience Report: New Plants." j September 1, 1987 Letter to applicant providing guidance on filing license amendment requests.
September 4, 1987 Issuance of bi-weekly Sholly notice regarding application ,
for sale and leaseback approval by El Paso Unit 3. l I
Palo Verde SSER 12 9 Appendix A
September 4, 1987 Issuance of Amendment No. 20 to Facility Operating License No. le F-41 and Amendment No.11 to Facility Operating Li-cense No. NPF technical specification changes to revise the level required for the condensate storage tank from 23 ft to an indicated level of 25 ft.
September 4, 1987 IssJance of Amendment No. 21 to Facility Operating License No. NPF technical specification changes regarding trip setpoints for low pressure in the steam generator and pressurizer, definition of an operable incore detection system, and required boration flow rate.
September 4, 1987 Letter to applicant regarding NUREG-1275 (Unit 3).
September 4, 1987 Letter from applicant forwarding revised pages for Reload Analysis Report.
September 8, 1987 Letter to applicant advising of acceptability of CEA Guide Tube Wear Inspection Program.
September 9, 1987 Meeting with applicant to discuss proposed amendment to the technical specifications on proposed revision to organizational structure.
September 10, 1987 Letter from applicant forwarding information on inservice testing program for pumps and valves.
September 10, 1987 Letter from applicant regarding SPOS audit open items.
September 14, 1987 Letter from applicant forwarding changes to the request for reload technical specification amendment - Units 2 and 3. ,
1 September 14, 1987 Letter from applicant regarding Unit 3 "B" diesel gener-ator bearing temperature monitor.
September 14, 1987 Letter from applicant forwarding 1986 annual reports.
September 15, 1987 Letter from applicant forwarding additional response to Item 2.1, Part 2 and Item 2.2 of Generic Ietter 83-28.
September 21, 1987 Letter from applicant providing response to Generic Letter-87-12, " Loss of Residual Heat Removal While the Reactor Coolant System Is Partially Filled."
September 22, 1987 Letter from applicant providing additional information re-garding proposed organizational changes.
September 22, 1987 Letter from applicant requesting approval of FSAR change to Structural Welding Code visual acceptance criteria to replace it with the Nuclear Construction Issues Group-Document.
Palo Verde SSER 12 E Appendix A
September 29, 1987 Issuance of Amendment No. 22 to Facility Operating License l No. NPF-41, Amendment No. 12 to Facility Operating License '
No. NPF-51, and Amendment No. 2 to Facility Operating Li-cense No. NPF technical specification chenges regard-ing the CEA Symmetry Test Program.
September 30, 1987 Letter to applicant regarding miscellaneous amendments /
search requirements.
October 1, 1987 Letter from applicant regarding proposed revision to spray pond monitoring program.
October 1, 1987 Letter from applicant regarding proposed amendment to temperature-dependent shutdown margin.
October 1, 1987 Letter from applic at forwarding revision to enrichment submittals (proposed reload amendment).
October 8, 198i Letter from applicant regarding reactor coolant pump shafts.
October 8, 1987 Letter from applicant forwarding change to the Initial Test P ogram.
October 8, 1987 Letter from applicant transmitting reports concerning Unit 3 "B" diesel generator. l October 9, 1987 Issuance of Amendment No. 23 to Facility Operating License No. NPF-41 and Amendment No. 13 to Facility Operating Li-cense No. NPF technical specification changes regard-ing shutdown margin requirements.
October 12, 1987 Letter from applicant forwarding responses to the lessons learned in NUREG-1275 (Unit 3).
October 15, 1987 Letter from applicant providing supplemental information regarding proposed organizational changes.
October 15, 1987 Letter to applicant regarding unescorted site access for L. E. Phillips.
I October 15, 1987 Letter from applicant concerning transfer switch modifica-tion for Unit 1.
October 19, 1987 Letter from applicant transmitting additional information on charging pump clamp.
October 19, 1987 Letter from applicant regarding revised approach to envi-ronmental qualification of safety-related equipment' located in a mild environment.
October 19, 1987 Letter from applicant confirming completion of certain con- ,
ditions of Unit 3 operating license.
1 Palo Verde SSER 12 11 Appendix A
October 21, 1987 Letter to applicant advising that inservice inspection pro-grams are acceptable, except for relief from certain ASME Code Section XI requirements.
October 21, 1987 Letter from applicant providing preliminary results of reactor coolant pump shaf t inspection for potential fatigue crac ki ng.
October 21, 1987 Letter to applicant confirming meeting on Class IE elec-trical inverters to be held October 26-27, 1987.
October 21, 1987 Issuance of Amendment No. 24 to Facility Operating License No. NPF technical specification changes for Cycle 2 operation.
October 24, 1987 Meeting with applicant to discuss reactor coolant pump shaft cracking problems at Unit 1. (Summary issued Novem-ber 3, 1987.)
October 24, 1987 Letter from applicant advising of implementation of aug-mented vibration monitoring program for each reactor coolant pump at Unit 2. )
l October 25, 1987 Issuance of Confirmatory Order Modifying License (Effec-tive Immediately) (regarding reactor coolant pump vibra-tion monitoring program), Unit 2.
October 29, 1987 Letter from applicant transmitting response to request for information on the Unit 1 piping verification test summary.
October 29, 1987 Letter from applicant regarding utility requalification training program.
October 29, 1987 Letter from applicant revising letters dated October 8 and 21, 1987 concerning reactor coolant pump shafts. i October 30, 1987 Issuance of Amendment No. 25 to Facility Operating License No. NPF-41, Amendment No. 14 to Facility Operating License i No. NPF-51, and Amendment No. 3 to Facility Operating Li-cense No. NPF technical specification change-s on organizational structure.
November 4, 1987 Meeting with applicant to discuss reactor coolant pump shaf t cracking problems. (Summary issued November 23, 1987.)
November 4, 1987 Letter from applicant transmitting Amendment 16 to Security Plan.
November 5, 1987 Letter from applicant advising of implementation of augmented I vibration monitoring program for reactor coolant pumps.
1 I
i Palo Verde SSER 12 12 Appendix A
November 10, 1987 Letter from applicant advising that discrepancy exists in 3 Specification 3.1.3.1, due to recently issued amendments I which af fect applicable modes - requesting correction by I errata pages. j November 12, 1987 Letter from applicant transmitting " Vibration Monitoring Program Elements," " Evaluation of Unit 1 and 2 Spectra Fre-quency Component Trends," and " Unit 1 RCP Shaft Crack Depth j Measurements."
November 13, 1987 Letter from applicant transmitting "Results of Leakage Monitoring Testing of Systems Outside Containment Which Could Contain Radioactive Fluids Following an Accident" (Unit 3).
November 19, 1987 Issuance of Confirmatory Order Modifying License (Effective Immediately) (regarding reactor coolant pump shaft monitor-ing program and shaft replacement), Unit 2.
l l
l Palo Wcde SSER 14 13 Appendix A
.q APPENDIX E ,
I ABBREVIATIONS APS Arizona Public Service Company CE Combustion Engineering CEA control element assembly CESSAR Combustinn Engineering Standard Safety Analysis Report CFR Code of Federal Regulations !
CPC core protection calculator FBI Federal Bureau of Investigation FSAR Final Safety Analysis Report IE Office of Inspection and Enforcement NRC Nuclear Regulatory Commission PASS postaccident sampling system PNM Public Service Company of New Mexico QA quality assurance RCP reactor coolant pump SER Safety Evaluation Report SPDS safety parameter display system SSER supplement to Safety Evaluation Report l
l l
Palo Verde SSER 12 1 Appendix E
- u. u.~uca. u.ool.To.,co . ,,04 , .,0 T~m...e. .., ..,,0c. ~ ..- ,,
~ge,,,
="A BIBUOGRAPHIC DATA SHEET NUREG-0857
$EE INSTRUC 5 04 T-E RE vtH51
- 2. T
- T L t AN D SL 'T LE J LE AVE BLANK Safety E luation Report Related to the Operation of Palo Verd Nuclear Generating Station, Units 1, 2 and 3 ,
Q,, , ,f, , coy,a , , o uoN1, u Aa l
. AUT-Oaisi Novemb 1987 j oAin . ,Oa r issuto
- n *a l
7 etRFOHuiN') ORGANtZ ATIO WE AND MA L4NQ AQQME$$ flec#wpp /g Codef dPRO No/'>mber uc T A$A WQRR UNil NUMStM 1987 Division of Rea or Projects - III, IV, V and Special Projec a
/
4 0a c.aA~ r Nuvana
(
Office of Nuclear . eactor Regulation
~
U.S. Nuclear Regul ory Commission j Washincton. D.C. t 555 /
IC $,0NSORING ORG ant 2 A TION N AME A- M AILING ADDRt$$ ttwfudy /p Cope # tia T YPE OF RtPOR T Safety Evaluation Report Same as 7. above ,,,,g,co,,,,,,,,,,,,,,
ia sue uuiNT Aav notes
\
l i
Docket Nos. STN 50-528, ST 50-529 and STN 5 -530 2 A sTa*ci am . ., u 1s
\
Supplement No. 12 to the Safe for the application filed by Arizona Public Service Company, et al,7 .for Evaluati lice sesn to Report operate the Palo Verde Nuclear Generating Station, Units 1, 2 and 3 (Doc (t Nos STN 50-528/529/530), located in Maricopa County, Arizona,' has been prepared by t' Of ice of Nuclear Reactor Regulation of'th e Nuclear Regulatory Commission. The purp. - of this supplement is to update the Safet, Evalu- .i ation Report by providing an eval tion of (1) additional information submitted Ny the licensee since Supplement No. 11 s issued and (2) other matters requiring staff *eview since Supplement No, 11 was iss ed, specifically those issues that required resolution j before Unit 3 full power lice ing.
f l
3 14 DocvMt NT ANALYS 5 - . Kive DS DESCR.,TCH$ }$ Av Angag,Lir v STATEYENT Palo Verde Nucl r Generating Station, Units 1* , and 3 Unlimited pipe crack C001 ant pump e secuairv cLAssi. c T3N as. ,
iot NT,,,e as. 0,s N sosoreaus Unclassified I f nog 1000r )
Unclassified 17NVM8tHOFPAGE$
18 PRtC E
- U,$. GOVCRhucht PelhithG Drr1CE i1997 202 792:60294 o
in dwwnnew:Mmsnmmtwwp#u%awksw4 M@tyne-tP$$$$$UMBES LUNITE iSTATES4 s hv v W N
MEMp%WF% 2$WMM N
M
" ~ " "
MEEoNaU1h [j ggn+1Ag "qNNGCLE p
i yn ;
- - e>~ .
~ -e wym g~g R HEG'ULITORY h4 :p R D@
m" u y ngpyp n n %9M kCONild s j d.*#
ps p3mmappp NJWR7M MM y d
N$M,jh$ WWWVP$*M-w.NIN[y.;p~y%g$
3 ,;b %y , n:- 60FFICIAL BUSINESScx~ WY N W N M N M g Wis . I MhNhM M c M W h W @ M S v
$)y$bf$jgw;pd MM M4my +y w n ; ' %wn QLk ,&~ ,wn% ,-n m
N '
a& n#a m.VNm .'x rMww w M%q Tt nq &)Mg[pr%e ly -;s j
% p u % y, y:Nolv p%
"; e ,
b ,a (4U^ uw')w.
0 y y/qw % .,y i $
n'y] % g ' +,M,:ygm [a-f 4
k(k w
%%g ,,, 7 "77 1 ja.
g mM#gp g$s k M fL N g^ WA - + r., -'%2:v tip%yM@Qg 1 w
W
$$m, ",<w, A 1
(hjf' u~ ,
w
-(7v; -
7vr=
> m - m-MQ w$ag#ge!Qh mqp g weg ,- v# w # a- ;,. .
D gg b Y $
eg g # w ;w& w, o #(\l ,
~ % y x ,m m ,,weegpd:gyy h
n- nnn,~_n.ene,,,, a ,
.w, w
3p y x m n .
m ,,w~ _7% ,
gm m ,
aa %pm_nunQ_u,a y
wg yw n mw 9%nm%;jpg,pq a a wsnm.ngm +
a x
. r m- ,% _,a w p e _g a w. w g o%M ~%
. c m_ w -
a p _ewh&gdgg an % g iqn
,M m%q$e g
p4
%em L
.o.. , s' a
. Jw %:
w W- ,
pnw mgMWqwgyanwMir nww g ymn wa %n%Nu ,m agd%Wwi w scam ux i .
aykq vgy Aq 8
+yQ ww, n m
em ?y
< M w a~h m a n s w wd h obQWWm fh 0hf c
~ y ij
. g- y , L 0 - '
$&m&p$?6kYh;kW t f
lj)Q%QMl ,
\ g;,e;u; mRM&q)pl:k&wlW l% W W? eNM hlrw ppgr &&d%qp%Q' $l;:#p$b)d'p$
%Q Wf