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Category:Inspection Report
MONTHYEARIR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion IR 05000528/20243012024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information IR 05000528/20230102023-08-22022 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000528/2023010, 05000529/2023010 and 05000530/2023010 IR 05000528/20230052023-08-21021 August 2023 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2023005 and 05000529/2023005 and 05000530/2023005) IR 05000528/20230022023-08-0808 August 2023 Integrated Inspection Report 05000528/2023002 and 05000529/2023002 and 05000530/2023002 IR 05000528/20233012023-06-0505 June 2023 NRC Examination Report 05000528/2023301, 05000529/2023301 and 05000530/2023301 IR 05000528/20230012023-05-0808 May 2023 and Independent Spent Fuel Storage Installation - Integrated Inspection Report 05000528/2023001 and 05000529/2023001 and 05000530/2023001 and 07200044/2023001 ML23115A4012023-04-26026 April 2023 Review of the 2022 Steam Generator Tube Inspections During Refueling Outage 23 IR 05000528/20230122023-04-19019 April 2023 Notification of Commercial Grade Dedication Inspection (05000528/2023012, 05000529/2023012, and 05000530/2023012) and RFI IR 05000528/20224012023-04-13013 April 2023 Cyber Security Inspection Report 05000528/2022401 and 05000529/2022401 and 05000530/2022401 IR 05000528/20234022023-03-29029 March 2023 and 3 - NRC Security Inspection Report 05000528-2023402, 05000529-2023402, and 05000530-2023402, (Cover Letter Only) IR 05000528/20220062023-03-0101 March 2023 Annual Assessment Letter for Palo Verde Nuclear Generating Station Units 1, 2 and 3 (Report 05000528/2022006, 05000529/2022006, and 05000530/2022006) IR 05000528/20234012023-02-27027 February 2023 NRC Security Inspection Report 05000528/2023401, 05000529/2023401, 05000530/2023401, and 07200044/2023401 (Full Report) IR 05000528/20220042023-01-30030 January 2023 Integrated Inspection Report 05000528/2022004 and 05000529/2022004 and 05000530/2022004 IR 05000528/20220102023-01-17017 January 2023 Design Basis Assurance Inspection (Teams) Inspection Report 05000528/2022010 and 05000529/2022010 and 05000530/2022010 IR 05000528/20220032022-10-24024 October 2022 Units, 1, 2 and 3 Integrated Inspection Report 05000528/2022003, 05000529/2022003, and 05000530/2022003 IR 05000528/20224032022-10-14014 October 2022 Security Baseline Inspection Report 05000528/2022403 and 05000529/2022403 and 05000530/2022403 ML22235A6662022-08-23023 August 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000528/2022010, 05000529/2022010, and 05000530/2022010) and Request for Information IR 05000528/20220052022-08-23023 August 2022 Updated Inspection Plan for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (Report 05000528/2022005 and 05000529/2022005 and 05000530/2022005) IR 05000528/20224022022-08-0808 August 2022 Cover Letter Only - Palo Verde Nuclear Generating Station, Units 1, 2, and 3 NRC Security Inspection Report 05000528 2022402, 05000529 2022402, 05000530 2022402, and 07200044 2022402 IR 05000520/20220022022-08-0505 August 2022 Integrated Inspection Report 05000528/2022002 and 05000529/2022002 and 05000520/2022002 IR 05000528/20223012022-06-21021 June 2022 NRC Examination Report 05000528/2022301, 05000529/2022301, and 05000530/2022301 IR 05000528/20220012022-05-0909 May 2022 Integrated Inspection Report 05000528/2022001, 05000529/2022001 and 05000530/2022001 ML22105A0512022-04-19019 April 2022 Review of the 2021 Steam Generator Tube Inspections During Refueling Outage 22 IR 05000528/20224202022-03-0808 March 2022 Security Baseline Inspection Report 05000528/2022420, 05000529/2022420 and 05000530/2022420, Cover Letter IR 05000528/20210062022-03-0202 March 2022 Annual Assessment Letter for Palo Verde Nuclear Generating Station - Units 1, 2 and 3 (Report 05000528/2021006, 05000529/2021006, and 05000530/2021006) IR 05000528/20210042022-02-0707 February 2022 Integrated Inspection Report 05000528/2021004, 05000529/2021004, and 05000530/2021004 IR 05000528/20210032021-11-12012 November 2021 Integrated Inspection Report 05000528/2021003, 05000529/2021003 and 05000530/2021003 IR 05000528/20210152021-10-27027 October 2021 Temporary Instruction 2515/194 Report 05000528/2021015 and 05000529/2021015 and 05000530/2021015 ML21273A3172021-10-0404 October 2021 Station. NON-SENSITIVE IR 05000528/20214042021-09-23023 September 2021 NRC Security Inspection Report 05000528/2021404, 05000529/2021404, 05000530/2021404 and 07200044/2021401 IR 05000528/20214012021-09-14014 September 2021 Security Baseline Inspection Report 05000528/2021401 and 05000529/2021401 and 05000530/2021401 IR 05000528/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Palo Verde Nuclear Generating Station - Units 1, 2 and 3 (Report 05000528/2021005, 05000529/2021005, and 05000530/2021005) IR 05000528/20210022021-08-0909 August 2021 Integrated Inspection Report 05000528/2021002, 05000529/2021002, and 05000530/2021002 and Exercise of Enforcement Discretion IR 07200044/20214012021-07-21021 July 2021 ISFSI, Information Request, Security Inspection Report 07200044/2021401 IR 05000528/20210142021-07-14014 July 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000528/2021014, 05000529/2021014 and 05000530/2021014 IR 05000528/20213012021-06-21021 June 2021 NRC Initial Examination Report 05000528/2021301, 05000529/2021301, and 05000530/2021301 IR 05000528/20214032021-05-28028 May 2021 Security Baseline Inspection Report 05000528/2021403; 05000529/2021403 and 05000530/2021403 (Public) 2024-08-08
[Table view] Category:Letter
MONTHYEARIR 05000528/20244042024-08-0808 August 2024 Cybersecurity Inspection Report 05000528/2024404, 05000529/2024404 and 05000530/2024404 ML24213A3232024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 71: Re-Submittal of RR-30 ML24213A3292024-07-31031 July 2024 Transmittal of Relief Request (RR) No. 72: Re-Submittal of RR-39 IR 05000528/20240022024-07-29029 July 2024 Integrated Inspection Report 05000528/2024002 and 05000529/2024002 and 05000530/2024002 ML24173A3302024-07-24024 July 2024 Pressurizer Surge Line Inspection Program ML24159A4702024-07-17017 July 2024 Issuance of Amendment Nos. 223, 223, and 223 Revision to Technical Specifications 3.5.1 and 3.5.2 Using Risk Informed Process for Evaluations ML24198A0662024-07-16016 July 2024 Program Review - Simulator Testing Methodology ML24193A3442024-07-11011 July 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 3R24 ML24129A0522024-07-0303 July 2024 Review of the Spring 2023 Steam Generator Tube Inspection Report ML24177A3212024-06-25025 June 2024 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX180, AMZDFX181, AMZDFX182 Vertical Concrete Cask Identification Nu IR 05000528/20240042024-06-25025 June 2024 Notification of Inspection (NRC Inspection Report 05000528/2024004, 05000529/2024004, 05000530/2024004) ML24170A9962024-06-18018 June 2024 Response to Second Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown a ML24129A2062024-06-14014 June 2024 Issuance of Amendment Nos. 222, 222, and 222 Revision to Technical Specifications to Adopt TSTF-266-A ML24159A0262024-06-0303 June 2024 Annual Report of Guarantee of Payment of Deferred Premium ML24135A2482024-05-14014 May 2024 Response to Second Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24164A2582024-05-0909 May 2024 10-PV-2024-04 Post-Exam Comments ML24128A2702024-05-0707 May 2024 Docket Nos. Stn 50-528/529/530 - Response to NRC Regulatory Issue Summary (RIS) 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24129A1482024-05-0707 May 2024 and Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Casks with Applied Changes IR 05000528/20240012024-05-0202 May 2024 Independent Spent Fuel Storage Installation, Integrated Inspection Report 05000528/2024001, 05000529/2024001, 05000530/2024001, 07200044/2024001, and Exercise of Enforcement Discretion ML24119A0022024-04-26026 April 2024 2023 Annual Environmental Operating Report ML24116A2082024-04-24024 April 2024 Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 IR 05000528/20244012024-04-22022 April 2024 Security Baseline Inspection Report 05000528/2024401 and 05000529/2024401 and 05000530/2024401 (Cover Letter) IR 05000528/20243012024-04-22022 April 2024 NRC Initial Operator Licensing Examination Approval 05000528/2024301, 05000529/2024301, and 05000530/2024301 ML24112A0012024-04-19019 April 2024 Core Operating Limits Report, Revision 32 ML24108A1982024-04-16016 April 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Casks with Applied Changes Authorized by an Amended Certificate of Compliance ML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24131A0972024-04-10010 April 2024 Annual Radiological Environmental Operating Report 2023 ML24096A2202024-04-0505 April 2024 Transmittal of Technical Specification Bases Revision 78 ML24032A1542024-04-0303 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24089A1892024-03-28028 March 2024 Present Levels of Financial Protection ML24068A2522024-03-0808 March 2024 License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Using Risk-Informed Process for Evaluations ML24066A0472024-03-0606 March 2024 Response to Request for Additional Information to Revise Technical Specifications (TS) 3.5.1, Safety Injection Tanks (Sits) – Operating, TS 3.5.2, Safety Injection Tanks (Sits) – Shutdown and TS IR 05000528/20240122024-03-0404 March 2024 Age-Related Degradation Inspection Report 05000528/2024012, 05000529/2024012 and 05000530/2024012 IR 05000528/20230062024-02-28028 February 2024 Annual Assessment Letter for Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Report 05000528/2023006 and 05000529/2023006 and 05000530/2023006 ML24053A3972024-02-22022 February 2024 License Renewal - Alloy 600 Management Program Plan ML24047A3632024-02-16016 February 2024 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Transportable Storage Canisters Identification Numbers AMZDFX177, AMZDFX178, AMZDFX179 Vertical Concrete Cask Identification No. AMZDNE179, AMZDNE178 IR 05000528/20230042024-02-12012 February 2024 Integrated Inspection Report Report 05000528/2023004 and 05000529/2023004 and 05000530/2023004 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owners Activity Report Number 1R24 ML24019A1362024-01-18018 January 2024 Inservice Inspection Request for Information ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line ML24010A1532024-01-10010 January 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection ML23341A0062023-12-21021 December 2023 Project Manager Assignment IR 05000528/20230112023-12-18018 December 2023 License Renewal Inspection Report 05000528/2023011 ML23335A0782023-11-30030 November 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1602023-11-17017 November 2023 Supplemental Submittal - Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20234032023-11-13013 November 2023 NRC Security Inspection Report 05000528 2023403, 05000529 2023403, 05000530 2023403 (Full Report) ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23299A3052023-10-26026 October 2023 Response to Request for Additional Information Relief Request 70 Proposed Alternatives for Pressurizer Lower Shell Temperature Nozzle IR 05000528/20230032023-10-17017 October 2023 Integrated Inspection Report 05000528 2023003 and 05000529 2023003 and 05000530 2023003 ML23270B9232023-09-28028 September 2023 Notification of Age-Related Degradation Inspection (05000528/2024012, 05000529/2024012, and 05000530/2024012) and Request for Information 2024-08-08
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION .
REGION V t
SUITE 202. WALNUT CREEK PLAZA I990 N. CALIFORNIA BOULEVARD WALNUT CREEK. CALIFORNIA 94596 Docket Nos. 50-528, 50-529, 50-530 hVR 1 L ~gp r
Arizona Public Service Company P. 0. Box 21666 Phoenix, Arizona 85036 Attention: Mr. E. E. Van Brunt, Jr.
Vice President, Construction Projects Gentlemen:
Subject:
NRC Investigation of Allegations Relating to Palo Verde Units 1, 2 and 3 This refers to the investigation conducted by Messrs. Garvin and Ward of this office on February 15-17, 1977 of activities authorized by NRC Construction Permit No. CPPR-141, 142 and 143, and to the discussion of our findings held by Mr. Garvin with you and Mr. J. Roedel of your staff at the conclusion of the investigation.
Areas examined during this investigation dealt with allegations of substitution of poor quality reinforcing steel for use at the Palo Verde construction site. Within this area, the investigation consisted of examination of procedures and records, interviews with Palo Verde and vendor personnel and observations by the inspectors.
No items of noncompliance with NRC requirements were identified within the scope of this inspection.
/
In accordance with Section 2.790 of the NRC's "Rules of Practice,"
Part 2, Title 10, Code of Federal Regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If this report contains any information that you believe to be proprietary, it is necessary that you submit a written application to this office, within 20 days of the date of this letter, requesting that such information be withheld from public disclosure. The applica-tion must include a full statement of the reasons why it is claimed that
'the information is proprietary. The application should be prepared so that any proprietary information identified is contained in an enclosure to the application, since the application without the enclosure will also be placed in the Public Document Room. If we do not hear from you
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Arizona Public Service Company MAR 1 t ig77 in this regard within the specified period, the report will be placed in the Public Document Room.
Should you have any questions concerning this inspection, we will be glad, to discuss them with you.
Sincerely, G. S. 'encer, Chief Reactor Construction and Engineering Support Branch
Enclosure:
IE Inspection Report No. 50-528, 529, 530/77-01 cc w/o enclosure:
Arthur C. Gehr, Esq Snell 5 'lJilmer 3100 Valley Center Phoenix, Arizona 85073 Hr. Carmine F. Cardamone, Jr.
1415 North Third Avenue Tucson, Arizona 85705
'EGION U. S. CLEAR REGULATORY COMMISSION
'OFFICE OF INSPECTION AND ENFORCEMENT V
IE Inspection Report Ho. 50-528 529 5 L'icensee Arizona. Publ,ic Service Com an 530 P. 0. Box 21666 License No. 142, 143 Phoeni x, Ari zona 85036 Priority Facility Pal o Verde Uni ts 1, 2, 3 Category A Location Mari copa County, Arizona Type of Facility PWR's (CE), 3800 MWt Type of Inspection Special, Announced Dates of Inspection February 15-17, 1977 Dates'f PrevioUs Inspection Oecember 14-17, 1976 Principal Inspector Date L. J. Garvin, Reactor Inspector
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Accompanying Inspectors HL M. J.'rd, Investigator Date Date Other Accompanying Personnel: None Reviewed by a/IP(~7 G. S. Spence, Chief, Reactor Construction and Date Engineering Support, Branch IE:V Form 219
Summar of Findin s Enforcement Action Hone Licensee Action on Previousl Identified Enforcement Items Not applicable Desi n Chan es None Other Si nificant Findin s The allegation of the substitution of bad reinforcing steel for use at the Palo Verde construction site appeared to be without merit.
Mana ement Heetin The inspector and investigator met with E. E. Van Brunt and J. Roedel at the conclusion of the investigation. No evidence had been found that could substantiate the allegations. The inspector stated that he had co'ncluded that the'einforcing steel being used at the Palo Verde site met the specification requirements.
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Details Persons Contacted Arizona Public Service Com an J. Roedel, gA tlanager E. E. Van Brunt, Jr., Vice President Marathon Steel Com an E. P. Bisntz, Vice President, Rolling tlill Division C. A. Bonacich, Manager, Fabrication Operations J. Stutz, Superintendent, f1elt Shop General The gA tlanager of Arizona Public Service (APS) telephoned the Region Y office on the after noon-- of February 10, 1977 to inform the region that another Federal agency was investigating allegations concerning the reinforcing steel that was being supplied to the Palo Verde construction site. The allegations appeared to be that substandard steel was being supplied to the construction site.. The subs'tan'dard steel was being substituted for acceptable steel by changing the heat numbers on the material control tags. (See paragraph 3 for the allegation.) The regional office was also informed that APS was conducting an investigation into the allegation.
(See paragraph 5 for licensee actions.)
On February 15-17, 1977 an inspector from the regional office and an investigator from IE:Hg conducted an investigation into the allegations. The inspectors examined the site for evidence of altered control tags. (See paragraph 6a for results of the inspec-tion of the construction site.) Also inspected was the vendor shop. (See paragraph 6b for the results of the inspection of the vendor shop.)
Alle ation As relayed to the inspectors by the other Federal agency the allegation involved changing heat numbers to get rid of bad steel.
Both heat numbers were on the back of the paper control tags that .
were being used in the shearing shop. The tags were being applied
.to the bar by the man cutting the bar and contained information for the persons bending the bars to final shape. Following cutting, the bars were taken to the forming area. During the forming/bending process some of the paper control tags were observed to have altered heat numbers. According to the alleger, when a supervisor was questioned about the altered numbers, his answer was "don't worry about't, we are getting rid of bad steel."
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- 4. ~Findin s d 1 heat numbers.
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~Findin : Observations at both the construction site and vendor shop. were that some paper tags had crossed out heat numbers.
The allegation was substantiated,.but this practice was per-mitted as discussed below.
- b. Bad Steel
~Ail.1:Bd11111 steel.
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~Findin :, Since both heat numbers (crossed out and new) were legible, the records could be reviewed for both heats. In all cases reviewed, the records proved that the material was acceptable. Observations at the vendor shop disclosed that changing'h'e heat number on the back of the control ta'g is a common practice. The practice is allowed by procedure and is used to,record the actual heat of material being sent to the construction site (see paragraph 6b). Discussion with workers at the vendor shop disclosed that only two heats of steel had failed the bend test. The steel that fails a bend test is acceptable for use at the construction site if used only as a straight bar. Both these heats were used in locations that required straight. bars. iso other heats had failed tests.
The allegation was not substantiated by observation, record review or discussion.
- 5. Licensee Action When informed of the allegations the licensee, in turn> informed the IE Region V office and then conducted an investigation of the matter.
Fifteen heat numbers of reinforcing steel were sampled and sent to a testing laboratory for chemical analysis. The controlling speci-fication, ASTH A615-74a, requires that the steel have less than 0.05'A. phosphorus. In all cases the phosphorus was less than the maximum allowable. The licensee did not attempt to verify that the heat numbers on the backs of the paper control tags had been changed or that the steel met the specified strength requirements.
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6.. Ins ectors'ctions Following the briefing on the*allegations, the inspectors visited the APS Huclear Project offices to review the licensee's actions.
The inspectors determined that the best course of action was a tour of the construction site to attempt to find, paper tags with altered heat numbers, followed by an inspection at the steel supplier's shop.
a ~ Construction Site Ins ection During a tour of the construction site the receiving sto'rage area was 'inspected. This area contained newly arrived bundles of reinforcing steel. During the inspection, 15 paper tags were collected that contained crossed out heat numbers.
It was estimated that approximately 5-10% of the tags examined contained crossed out heat numbers. Approximately 25Ã of the paper tags in the receiving area were examined. Waste containers were also examined during the site tour. One paper tag with marked out numbers was collected from a waste container.
Several of the crossed out numbers appeared more than once on the collected paper tags, therefore, the backs of the tags contained only 15 heat numbers which were either the original marked out numbers, or new numbers. Both the crossed out heat numbers and the new heat numbers were legible, so the inspectors were able to examine the mill "report of chemical analysis and/or physical properties" for all heat numbers. In all cases both heat numbers had reports on file at the construction site. These reports indicated that both heat numbers (crossed out and new number) were numbers of acceptable material. All properties met contract and ASTM requirements.
- b. Vendor Sho Ins ection The basic raw material used by the Marathon Steel Company to produce reinforcing steel is shredded automobile bodies. The bodies are melted in electric furnaces and samples taken for spectrographic analysis. The analysis is fed directly to the computer control system which determines the chemical additions needed, to adjust the molten steel so that an acceptable product is assured. After the additions, the molten material is poured into approximately 45 one thousand-pound ingots. While the 15th ingot is being poured a final "official" sample is taken for spectrographic analysis. The results become the official chemical analysis for the heat of steel. Each ingot is marked with the heat number and is stored until needed.
Reinforcing bar is produced from the ingots when bar stored for the construction site is running low. All the ingots from a heat of steel are heated and then rolled in successively, smaller rolling machines until the desired bar diameter is reached. These bars are then bundled, heat number tagged and stored. Samples are taken for the strength, ductility and bend tests. These test results confirm the quality of the reinforcing steel and become part of the mill certification record.
8ars are removed from storage and taken to the shear shop where they are cut to the desired length and tagged with a control tag. This control tag contains information about the ba'r's length and its final snape following bending in the forming shop. The information supplied on the control tag comes from the cut sheet (drawing that contains shape and dimensions) and the heat number tag on the bundle. The shear machine operator places the heat number on the back of the control tags for several bars before he shears the bars to the desired lengths. If he overestimates the quantity of bars in a bundle he must correct the heat number he had previously written on the back of the control tags. In that case he crosses out the first heat number and replaces it with the actual heat number of the bar that he cuts to the desired length. The actual heat number is also written as a double check on the cut sheet. The cut sheet is sent to the office where metal control tags are stamped. The metal tags are applied to the bars in the forming shop after the bars have been bent into the shape described on the paper control tags.
The final step is loading the bars on trucks for the trip to the construction site.
Several altered tags were discovered during the inspection at the vendor shop. Discussions with several workers and the supervision indicated that the above description of the reason for. the altered tags is correct. The cut sheets for the altered tags were compared and in each case the new heat number on the cut sheet agreed with the altered number on the tag.
Sho Record Review To double check the mill properties, the shop records for heat numbers compiled from the paper control tags collected at the construction site were also reviewed. The following heat numbers were reviewed.
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Heat Number Bar Size 31263 18 28798 18 20017 18 31250 18 20187 18 20172 18 32168 6 32197 .6 20578 18 20571 18 32012 18 32005 18 31'913 18 20510 18 20508 18 The record review indicated that each heat of steel met all requirements.
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION V SUITE 202. WALNUT CREEK PLAZA r I990 N. CALIFORNIA BOULEVARD WALNUT CREEK, CALIFORNIA 94596 Docket Nos. 50-528, 50-529, 50-530.
bQR 1:- Ii;(
i~1EMORANDUM FOR: G. M. Roy, Chief, Field Coordination and Enforcement Branch, IE:Hg FROf1: G. S. Spencer, Chief, Reactor Construction and Engineering Support Branch, IE:V
SUBJECT:
ARIZONA PUBLIC SERVICE COMPANY (PALO VERDE UNITS 1,,2 AND 3)
Enclosed is a report of an investigation at the subject facilities.
This investigation was conducted on February 15-17, 1977. The alle-gations were not substantiated. It appeared to our inspector that the allegation was the result of a misunderstanding.
G. S. S encer, Chief Reactor Construction and Engineering Support Branch
Enclosures:
Ltr to APS w/IE Inspection Report No. 50-528, 529, 530/77-01
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