IR 05000295/1987020

Insp Repts 50-295/87-20 & 50-304/87-21 on 870817-27.No Violations Noted.Major Areas Inspected:Previous Insp Findings,Control Rod Testing,Shutdown Margin/Estimated Critical Calculation & Core Power Evaluation

ML20234B334
Person / Time
Site:	Zion  File:ZionSolutions icon.png
Issue date:	09/10/1987
From:	Azab B, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20234B234	List: IR 05000295/1987020 ML20234B232
References
50-295-87-20, 50-304-87-21, NUDOCS 8709180365
Download: ML20234B334 (6)

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• U.S. NUCLEAR REGULATORY COMMISSION'

REGION III {

Reports No. . 50-295/87020(DRS); 50-304/87021(DRS) )

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Docket-Nos. 50-295;'50-304 Licenses No. DPR-39; OPR-48 I

' Licensee: ' Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Zion Nuclear Power Station, Units 1 and 2 Inspection'At: Zion Site,' Illinois Inspection Conducted: August 17-27, 1987 Inspector:

Ih B7 A. Azdib p .

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Approved By:

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. C. Wrigt t, Chief 9[/d 2 -

Test Programs'Section Date l

Inspection Summary Inspection on August 17-27, 1987 (Reports No. 50-295/87020(DRS); )

50-304/87021(DRS)) l Areas Inspected: Routine, unannounced, safety inspection of licensee action !

on previous inspection findings (92701 and 92702), control rod testing (72700), j shutdown margin / estimated critical condition calculation (61707), control rod  !

. worth measurements (61710), core power distribution limits (61702), core j thermal power evaluation (61706), and isothermal and moderator temperature coefficient determinations (61708).

Results: No violations or deviations were identifie ,

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i 8709180365 870911 PDR ADOCK 05000295-G PDR.

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DETAILS Person' Contacted

• George J. Plim1, Station Manager  !

*Jerry Ballard, Quality Control Supervisor  !

• Mark M. Holzmer, Senior Resident Inspector

• Feter LeBlond, Nuclear Licensing Administrator

• Randall E. Mika,' Assistant Technical Staff Supervisor

• Ronald J. Niederer, Nuclear Group Leader

• Carl Schultz, Regulatory Assurance Supervisor

• Willie Stone, Station Quality Assurance Superintendent E. H. Young, Nuclear Fuels Services  ;

The inspector also interviewed other licensee personnel during  ;

the course of the inspection including members of the technical  !

and operations. staf * Denotes persons attending the exit meeting on August 27, 1987. Licensee Action on Previous Inspection Findings (92701 and 92702). j (Closed) Violation (304/86011-02a): Two errors were made in the calculation of control rod withdrawal limits which assure a negative moderator temperature coefficient (MTS); which the licensee failed to identify.and correct. The licensee's immediate corrective actions-were to re-review and correct the identified errors. . The following actions have been taken to prevent recurrence: (1) addition of the equation, "ITC = MTC + DTC" to Procedure TSS 15.6.54, " Isothermal Moderator Temperature Coefficient Measurements." (2) A new procedure, 1 TSGP-40, " Calculation of Conditions to Assure that the Reactor Moderator Temperature Coefficient is Negative," has been written and 4 implemented to provide instructions for calculating rod withdrawal limits. (3) Members of the Nuclear Group were given training in meetings held July 22-24, 1987, on proper performance of procedure The inspector has no further concerns in this area, (Closed) Violation (295/86012-02b): Procedure steps were skipped ,

or not signed before proceeding to the next steps. A " performance l review signature" has been added to all startup testing procedures to signify that the procedure steps are complete and continuation ,

of the reactor startup sequence is permissible. Final review of i test results is being performed in a more timely manner (usually ;

within one or two days of completing each test). Members of the Nuclear-Group received training on July 22-24, 1987, which included instructions on performing procedure steps in the proper sequenc *

The inspector has no further concerns in this area, i (Closed) Unresolved Item (295/85027-03): An error was made in the calculation of the MTC component of the isothermal temperature l coefficient (ITC) reported in Table 7.2 of the Nuclear Design Report i

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(NDR) for Unit 1, Cycle 9. A +1 pcm/ F which is normally added to the MTC to counteract model deficiencies was not added. Table was corrected via a memo from H. E. Bliss, Nuclear Fuels Services Manager to K. L. Graesser, Zion Station Manager, " Revision to Table 7.2 of Zion, Unit 1 Cycle 9 Nuclear Design Report," Z109/045,  !

dated August 2, 1985. The "NDR Generation Procedure," NSF-PND-301, was revised to include written instructions for adding the +1 pcm/ F bias to prevent recurrence of this event. The inspector has no further concerns in this are (Closed) Unresolved Item (295/86012-01; 304/86011-01): The K(z)

figure in Technical Specifications, Figure 3.2-9, developed by '

Westinghouse, was incorrect. The error was discovered by Westinghou e during a review of the Zion 1 Cycle 10 Reload Safety Evaluation. An immediate corrective action was to change the K(z)

inputs to the computer code. A Technical Specification Change to correct the K(z) figure was submitted to the NRC on October 10, 1986, and was completed on February 26, 1987. Commonwealth Edison Company's '

Quality Assurance Department performed an audit of Westinghouse's Nuclear Fuel Design Control, which concluded that the Westinghouse corrective action was sufficient to prevent recurrence of a K(z)

error. Because the error was not discovered by Ceco's Nuclear Fuels Services' (NFS) review, a new internal NFS procedure is being developed to review externally generated analyses. This item will remain an Open Item (295/87020-01; 304/87021-01) pending completion and an NRC review of the NFS procedur No violations or deviations were identified; however, a portion of this area requires further revie . Control Rod Testing (72700) ,

The inspector reviewed the following completed surveillance and verified that the control rod system was fully operational and the test results complied with Technical Specifications 3. * TSS 15.6.26, " Control Rod System Checkout," performed for Unit 2 on July 29, 198 * TSS 15.6.57, " Rod Drop and Timing Test," completed l July 31, 198 !

I No violations or deviations were identifie . Shutdown Margin / Estimated Critical Condition Calculation (61707)

l In the area of shutdown margin and estimated critical condition l calculations, the inspector reviewed various procedures and their results for technical adequacy and compliance with Technical Specifications 3/4.2.1. The following documents were employed during the review:

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• " Zion 2,~ Cycle ~10 Nuclear Design Report." J

• TSS 15.6.51, "Zero Power Physics Measurements Following Refueling," performed August 1, 198 'o TSS 15.6.52, " Initial Criticality After-Refueling and Nuclear ;

Heating Level," performed July 31 through August 1, 1987, for !

Unit * TSS 15.6.51, " Reactivity Anomaly Check," performed August 1,- 198 j No violations or deviations were identifie ._ Control Rod Worth Measurements (61710)

The inspector reviewed TSS 15.6.53, " Boron Endpoint Measurement" and

TSS 15.6.55, " Rod and Boron Worth Measurements," for technical adequacy

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and compliance with Technical Specification 4.2.1.D.2. The measured rod

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worths agreed with the predicted rod worths recorded in the Nuclear Design Report and were well within the design acceptance criteri l l

During review of TSS 15.6.55, the inspector identified one concern. .An !

initial condition for several startup tests is the reactor coolant system I (RCS) must be in " boron equilibrium" which is defined in Section 4.0 of l TSS-15.6.51,."Zero Power Physics Measurements," (the controlling document i for startup physics testing). However, TSS 15.6.54, " Isothermal Moderator Temperature Coefficient Measurements" and TSS 15.6.55 while requiring

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the RCS to be in boron equilibrium, give different definitions for bcron i equilibrium than that stated in TSS 15.6.51. In response to the inspector's concern, procedure changes were initiated to eliminate the l

discrepancies in the definitions and adopt the ANSI 19.6.1, " Reload Startup Physics Tests for Pressurized Water Reactors" recommended i definition for boron equilibrium in all three procedures. The inspector ,

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has no'further concerns in this are No violations or deviations were identifie ,

f Core Power Distribution Limits (61702)

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The inspector reviewed a number of procedures and test results concerning core power distribution limits, and verified that they were technically l adequate, performed with the proper frequency, and complied with Technical !

Specification requirements. The following documents were used during the i review: 1

• TSS 15.6,0, " Flux Map Data Acquisition, Power Distribution and Incore/Excore Axial Inbalance Checks."

• PT-0 Appendix I, "Excore Detector Outputs and Quadrant Power Tilt Ratio Shif t Checklist Data Sheet 1."

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• TSS 15.5.1, " Determination of Delta-I Operating Limits."

• ZNG 87-106 and ZNG 87-109, letters to the Operating Engineer Unit 2 from the Nuclear Grou The inspector identified one errer made in the calculation of the total hot channel factor limit for Flux Nap No. 3, on Table 1 of TSS 15.6.0, performed on August 10, 198 Although the error was in i the non-conservative direction, it was noted that the actual total hot '

channel factor was much less than the limit, therefore, there was no safety concern. The Nuclear Group Leader immediately had the error re-reviewed and corrected. No other calculational errors were identified; this was considered an isolated inciden The inspector has no further l concerns in this are No violations or deviations were identifie . Core Thermal Power Evaluation (61706)

The inspector reviewed a two week sample of the completed surveillance, PT-0 Appendix M, " Calorimetric" and verified that heat balances were performed daily and the nuclear instrumentation system's power range channels were properly adjusted to equal the calorimeter power when require No violations or deviations were identifie . Isothermal and Moderator Temperature Coefficient Determinations (61708)

The inspector reviewed the following two procedures in the area of isothermal and moderator temperature coefficient (MTC) determinations: TSS 15.6.54, " Isothermal and Moderator Temperature Coefficient Measurements," is used to perform heat-ups and cool-downs at zero power to obtain measured values for ITC and MT TSGP-40, " Calculation of Conditions to Assure that the Reactor Moderator Temperature Coefficient is Negative," uses the measured MTC values from TSS 15.6.54 to establish a plot of reactor parameters (Control Bank D position, boron concentration, and average temperature) which is used to maintain a negative MTC during operation. The MTC values from TSS 15.6.54 are first adjusted to the same core conditions, then an error factor of 0.5 pcm/ F is added to obtain one value of MTC used to generate the rod withdrawal limits curve. One of the adjusted MTC values fell outside of the 0.5 pcm/ F error and was greater than the MTC used to establish the curve. Neither the Nuclear Group nor NFS knew the basis for the 0.5 pcm/ F error, but are currently investigating i This will be an Open Item (304/87021-02) pending an NRC review of the basis for the 0.5 pcm/ F erro _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _

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No violations or deviations were identified, however, a portion of this area requires further NRC revie . Open Items Open Items are matters which have been discussed with the licensee, will be reviewed further by the inspector, and involve,some action on the part of the NRC, licensee, or both. Two Open Items identified during the inspection are discussed in Paragraphs 2d and 8 . Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)

on August 27, 1987. The inspector summarized the scope and findings of the inspection. The licensee acknowledged the statements made by the inspector with respect to the Open Items. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspectio The licensee acknowledged statements made by the inspector and stated that the Ceco Nuclear Design Report referenced within this repor'. was considered proprietary, but references to the document would not be considered proprietar l l

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