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{{Adams | |||
| number = ML20132C589 | |||
| issue date = 09/20/1985 | |||
| title = Insp Repts 50-295/85-27 & 50-304/85-28 on 850722-0830.No Violation or Deviation Noted.Major Areas Inspected:Reactor Thermocouple/Rtd Cross Calibr,Isothermal Temp & Doppler Coefficient Measurements | |||
| author name = Mccormickbarge, Ring M | |||
| author affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) | |||
| addressee name = | |||
| addressee affiliation = | |||
| docket = 05000295, 05000304 | |||
| license number = | |||
| contact person = | |||
| document report number = 50-295-85-27, 50-304-85-28, NUDOCS 8509270095 | |||
| package number = ML20132C583 | |||
| document type = INSPECTION REPORT, NRC-GENERATED, INSPECTION REPORT, UTILITY, TEXT-INSPECTION & AUDIT & I&E CIRCULARS | |||
| page count = 10 | |||
}} | |||
See also: [[see also::IR 05000722/2008030]] | |||
=Text= | |||
{{#Wiki_filter:. | |||
-U.S. NUCLEAR REGULATORY COMMISSION | |||
REGION III | |||
Report Nos. 50-295/85027(CRS); 50-304/85028(DRS) | |||
Docket Nos. 50-295; 50-304 License Nos. DPR-39; DPR-48 | |||
Licensee: Commonwealth Edison Company | |||
.P. O. Box 767 | |||
Chicago, Illinois 60690 | |||
Facility Name: Zion Nuclear Power Station, Units 1 and 2 | |||
Inspection At: Zion, Illinois | |||
Inspection Conducted: July 22 through Auge t 30. 1985 | |||
IfM.}l.d Y Dtd d' M | |||
Inspector: bcCormick-Barger b28- h5 | |||
Date | |||
3 _ | |||
0 S 9 ()V | |||
Approved By: M. A. Ring, Chief | |||
Test Programs Section Date | |||
Inspection Summary | |||
Inspection on July 22 through August 30, 1985 (Report No. 50-295/85027(DRS); | |||
50-304/85028(DRS)) | |||
Areas Inspected: Routine, announced inspection of licensee actions on | |||
previous inspection findings, general program requirements for Unit 1 | |||
Cycle 9 Startup Testing, reactor thermocouple /RTD cross calibration, | |||
isothermal temperature coefficient measurement, doppler coefficient | |||
measurement, control rod drive and rod position indication checks, and | |||
incore/excore calibration. The inspection involved 94 inspector-hours | |||
onsite. | |||
Results: No violations or deviations were identified. | |||
0 | |||
8509270095 | |||
ADOCK | |||
850 295 | |||
PDR PDR | |||
G | |||
_ _ _ _ _ _ _ _ _ _ | |||
. | |||
. | |||
DETAILS | |||
1. Persons Contacted | |||
*K. Graesser, Station Manager | |||
*T. Rieck, Station Superintendent, Services | |||
*W. Kurth, Assistant Superintendent, Services | |||
*C. Schultz, Assistant Technical Staff Supervisor | |||
*R. Chin, Nuclear Group Leader | |||
*W. Stone, Quality Assurance Supervisor | |||
*J. Ballard, Quality Control Supervisor | |||
Additional station technical and administrative personnel were | |||
contacted by the inspector during the course of the inspection. | |||
* Denotes those personnel present at the exit interview. | |||
2. Licensee Action on Previous Inspection Findings | |||
(Closed) Open Item (295/82-21-01): This item involved two concerns - | |||
the lack of acceptance criteria for the wide range Resistance Temperature | |||
Detectors (RTD) in surveillance procedure TSS 15.6.72, "RTD Cross | |||
Calibration," dated November 10, 1981 and that 15 of the 65 incore | |||
thermocouples for Unit 1 Cycle 7 were inoperable. | |||
The inspector reviewed TSS 15.6.72, "RTD Cross Calibration," dated | |||
September 20, 1984, and noted that it contained the following acceptance | |||
criterion for the wide range RTDs: " Step 6.13. Evaluate the wide range | |||
RTDs using the following acceptance criterion: -6 F 1 (predicted wide | |||
range RTD temperature - average temperature of all the good narrow range | |||
RTDs) 5 0.5 F." A review of the incore thermocouples for operability | |||
based on the results of TSS 15.6.72, dated September 20, 1984, and | |||
performed for Unit 1 Cycle 9 on September 7-13, 1985, indicated that | |||
only 5 of 65 incore thermocouples were inoperable which the inspector | |||
cormiders acceptable. | |||
3. General Program Requirements for Unit 1 Cycle 9 Startup Testing | |||
The inspector utilized the following documents during a review of | |||
general program requirements for Unit 1 Cycle 9 Startup Testing: | |||
* Reload Safety Evaluation Zion Nuclear Plant, Unit 1 | |||
Cycle 9, July 1984. | |||
* NRC letter J. Norris to D. L. Farrar, NRC transmittal | |||
of Technical Specification Amendments No. 89 to DPR-39 | |||
and No. 79 to DPR-48 and the associated safety evaluation 1 | |||
' | |||
report, dated May 24, 1985. | |||
2 | |||
. _ _ _ _ _ - _ - _ _ | |||
. | |||
. | |||
* Commonwealth Edison (CECO) Internal Memorandum, | |||
H. E. Bliss, Nuclear Fuel Services Manager, to | |||
K. L. Graesser, Zion Station Manger, " Zion 1 Cycle 9 | |||
CAOC Analysis Based on Actual E0C8 Burnup," Z1C9/043, | |||
dated June 7, 1985. | |||
* Safety Parameter Interaction List for Zion, Unit 1 | |||
Cycle 9, approved January 4,1984. | |||
* Zion 1, Cycle 9, Nuclear Design Report, NFSR-0035, | |||
Revision 0. | |||
l | |||
* CECO memo, H. E. Bliss to K. L. Graesser, " Revision | |||
; | |||
to Table 7.2 of Zion, Unit 1 Cycle 9 Nuclear Design | |||
Report," dated August 2, 1985. | |||
' | |||
* CECO memo, H. E. Bliss to K. L. Graesser, " Zion 1 | |||
Cycle 9 Rod Exchange Data," Z1C9/040, dated May 9, 1985. | |||
* Technical Staff Surveillance (TSS) Procedure 15.6.51, | |||
"Zero Power Physics Measurements Following Refueling," | |||
dated June 3, 1985 and performed for Unit 1 Cycle 9 | |||
on June 14-16, 1985. | |||
* TSS Procedure 15.6.61, "At Power Physics Measurements | |||
Following Refueling," dated January 10, 1984, and | |||
performed for Unit 1 Cycle 9 on June 21, 1985 | |||
to July 27, 1985. | |||
With regard to TSS 15.6.51, "Zero Power Physics Measurements Following ' | |||
Refueling," the results evaluation discussed inconsistencies in boron | |||
sample measurements taken during startup physics testing. Boron sample | |||
measurement inconsistencies were also identified in the results | |||
evaluation for TSS 15.6.51, dated July 2, 1984, and performed for Unit 2, | |||
Cycle 8 on July 4-7, 1984. For Unit 1 Cycle 9, differences between two | |||
measurements of the same boron sample were as much as 67 ppm and, | |||
for Unit 2 Cycle 8, were as much as 45 ppm. The corrective actions | |||
discussed in the Unit 2 Cycle 8 test evaluation recommended that a | |||
meeting be held between the Nuclear Group and the station chemists to | |||
discuss the importance of boron sampling measurements. Although no | |||
meeting minutes were kept, the Station Nuclear Engineer stated that | |||
this meeting had taken place prior to the Unit 1 Cycle 9 startup. To | |||
calibrate the boron measurement instrumentation, a standard with known | |||
boron concentration is used. In an attempt to improve boron sample | |||
measurements, the Unit 1 Cycle 9 test evaluation indicated that the | |||
licensee intends to investigate the possibility of using a standard | |||
with a boron concentration nearer to the boron concentration of the | |||
samples being measured. Review of the licensee's corrective actions | |||
in a subsequent NRC inspection will be tracked as an open item | |||
I | |||
L | |||
(295/85027-01). | |||
I | |||
.s | |||
3 | |||
i | |||
k . . | |||
. | |||
. | |||
. . . . _ _ - _ _ _ _ _ - _ - _ _ _ - | |||
TSS 15.6.51 and TSS 15.6.61 both contained steps requiring that the | |||
manufacturer, model and serial number of all instruments used in the | |||
reactivity computer system be recorded. In both cases, the inspector was | |||
unable to locate this information in the completed test packages. In | |||
discussions of this matter with the licensee, the licensee explained | |||
that, since Zion has only one reactivity computer system, a standard | |||
type written sheet had been developed which provided all of this | |||
information. This sheet was inadvertently omitted from the completed | |||
test packages. The licensee stated their intent to take the necessary | |||
actions to ensure that future test packages include reactivity computer | |||
system data as required. | |||
Paragraph 5.a of this report contains comments regarding the Zion 1 | |||
Cycle 9 Nuclear Design Report and CECO memo, " Revision to Table 7.2 of | |||
Zion, Unit 1 Cycle 9 Nuclear Design Report," dated August 2, 1985. | |||
No violations or deviations were identified. However, a portion of this | |||
area requires further review and evaluation and is considered to be an | |||
open item. | |||
4. Reactor Thermocouple /RTD Cross Calibration | |||
The inspector reviewed surveillance procedure TSS 15.6.72, "RTD Cross | |||
Calibration," dated September 20, 1984, and performed for Unit 1 Cycle 9 | |||
on June 7-13, 1985, to determine that results obtained were within | |||
prescribed limits and that any discrepancies were properly evaluated. | |||
During this review the inspector noted that the results for one of the | |||
wide range RTDs did not meet the acceptance criterion for wide range RTDs | |||
of: "-6 F <_ (predicted wide range RTD temperature minus the average | |||
temperature of all the good narrow range RTDs) < 0.5 F." The licensee | |||
stated that an evaluation of this condition tooE place prior to proceeding | |||
with the Unit 1 Cycle 9 initial startup. The inspector had no evidence | |||
that would contradict that statement. However, the documented evaluation | |||
was not signed until June 27, 1985. (The test which was required to be | |||
performed prior to initial criticality was performed on June 12-13, 1985, , | |||
initial criticality occurred on June 14, 1985, and Unit 1 was at 88% power | |||
' | |||
on June 25, 1985.) In discussions with the licensee concerning this | |||
matter, the licensee agreed that, in the future, the evaluation of a | |||
startup test acceptance criterion that was not satisfied would be | |||
documented prior to proceeding with the startup testing. This is an | |||
open item pending NRC review during the next core physics startup | |||
testing inspection (295/85027-02). | |||
No violations or deviations were identified. However, a portion of this | |||
area requires further review and evaluation and is considered to be an , | |||
open item. ) | |||
5. Isothermal Temperature Coefficient and Doppler Coefficient | |||
The inspector reviewed licensee procedures and results to verify that | |||
prerequisites, precautions and plant conditions were met, that results | |||
4 | |||
were within acceptance criteria and consistent with Technical | |||
Specifications and that any discrepancies were properly evaluated. | |||
The inspector utilized the following procedures during the review: | |||
* TSS 15.6.54, " Isothermal Moderator Temperature Coefficient | |||
Measurements," dated May 27, 1982, and performed for Unit 1 | |||
Cycle 9 on June 15, 1985. | |||
* TSS 15.6.62, " Moderator Temperature Coefficient Measurement," | |||
dated July 9, 1980, (with Station Procedure Change Request | |||
A85-613 approved June 27, 1985, attached) and performed for | |||
Unit 1 Cycle 9 on July 9, 1985. | |||
* TSS 15.6.62, " Moderator Temperature Coefficient Measurement," | |||
dated July 9,1980, (with Station Procedure Change Request | |||
A85-613 approved June 27, 1985, attached) and performed for | |||
Unit 1 Cycle 9 on July 27, 1985. | |||
* TSS 15.6.63, " Doppler Coefficient Measurement," dated | |||
February 8, 1985, (with Station Procedure Change Request | |||
A85-612 approved June 27, 1985, attached) and performed for | |||
Unit 1 Cycle 9 on July 9, 1985. | |||
* TSS 15.6.63, " Doppler Coefficient Measurement," dated | |||
February 8, 1985, (with Station Procedure Change Request | |||
A85-612 approved June 27, 1985, attached) and performed for | |||
Unit 1 Cycle 9 on July 22, 1985. | |||
The inspector also utilized the following document during the review: | |||
* " Nuclear Design Report for Zion, Unit 1 Cycle 9," NFSR 0035, | |||
Revision 0, Nuclear Fuel Services - Commonwealth Edison Company, | |||
dated April 1985. | |||
a. During the test evaluation for TSS 15.6.54, " Isothermal Moderator | |||
Temperature Coefficient Measurements," performed on June 15, 1985, a | |||
member of the Technical Staff discovered an apparent error in | |||
Table 7.2 of the Nuclear Design Report. In discussions between the | |||
Technical Staff and the Nuclear Fuel Services Section, it was | |||
confirmed that an error existed in the method used to generate the | |||
moderator temperature coefficient component of the isothermal | |||
temperature coefficient reported in Table 7.2. Table 7.2 was | |||
subsequently corrected via a memo from H. E. Bliss, Nuclear | |||
Fuel Services Manager, to K. L. Graesser, Zion Station Manager, | |||
" Revision to Table 7.2 of Zion, Unit 1 Cycle 9 Nuclear Design | |||
Report," Z1C9/045, dated August 2, 1985. Other than this memo, | |||
members of the Technical Staff were not cognizant of corrective i | |||
actions taken by the Nuclear Fuel Services section. Therefore, l | |||
pending an NRC inspection of the CECO Nuclear Fuel Services section l | |||
to review the licensee's corrective actions to prevent recurrence l | |||
of errors in nuclear design reports, this is considered an unresolved | |||
item (295/85027-03). | |||
5 | |||
.-- -_-- | |||
1 | |||
-- | |||
- _ _ _ - . - - - - - - - - - - - - - _ _ _ _ , | |||
. | |||
b. The test evaluation for TSS 15.6.63, " Doppler Coefficient | |||
Measurement," performed on July 9, 1985, stated that all design | |||
and safety criteria were met. However, the measured doppler | |||
coefficient was -7.59 pcm/% power which was outside of the design | |||
acceptance criterion band of -8.95 1.34 pcm/% power (i.e., | |||
-7.61 to -10.29 pcm/% power). At the time that the inspector | |||
reviewed the test evaluation, the Technical Staff Supervisor had | |||
not signed the procedure yet. Additionally, a subsequent doppler | |||
coefficient measurement had been performed on July 22, 1985, which | |||
resulted in a doppler coefficient value that did meet the design l | |||
acceptance criterion. Following discussion of this matter with the ' | |||
licensee, the licensee rewrote the test evaluation to reflect the | |||
fact that the design acceptance criterion for the doppler coefficient | |||
had not been met in the July 9 instance. | |||
No violations or deviations were identified. However, a portion of this | |||
area requires further review and evaluation and is considered to be an | |||
l unresolved item. | |||
6. Control Rod Drive and Rod Position Indication Checks | |||
i | |||
f The inspector reviewed licensee procedures and results to verify that | |||
} prerequisites, precautions and plant conditions were met, that results i | |||
l' were within acceptance criteria and consistent with Technical l | |||
Specifications and that any discrepancies were properly evaluated. | |||
The inspector utilized the following procedures during the review: | |||
* TSS 15.6.26, " Control Rod System Checkout," dated | |||
January 1, 1985, and performed for Unit 1 Cycle 9 | |||
on June 10-12, 1985. | |||
* TSS 15.6.57, "Checkcut of the Bank Overlap Unit," | |||
dated March 12, 1984, and performed for %it 1 | |||
Cycle 9 on June 11, 1985. | |||
a. With regard to TSS 15.6.26, " Control Rod System Checkout," | |||
the inspector noted the following: | |||
(1) All rod drop times satisfied the acceptance criterion | |||
of 2.4 seconds or less required by the Technical | |||
Specifications. | |||
(2) The inspector reviewed the slave cycler strip chart traces | |||
for power cabinets 180 and 1AC and the rod drop timing traces | |||
for rods in Shutdown Banks A, C, and D, and Control Bank A. | |||
The inspector had no cor,cerns as a result of the review of | |||
these strip charts. | |||
(3) Surveillance test TSS 15.6.26 was required to be completed | |||
prior to initial criticality per Technical Specification 3/4.2.3.C. | |||
However, the signatures in the last section of the procedure | |||
(the test results evaluation section) were as follows: | |||
6 | |||
. | |||
. | |||
! | |||
Initial Criticality, June 14, 1985 | |||
Test Engineer's Signature, June 21, 1935 | |||
(Reactor at approximately 49% power) | |||
l Station Nuclear Engineer's Signature, July 10, 1985 | |||
! | |||
(Reactor at approximately 100% power) | |||
Technical Staff Supervisor's Signature, July 19, 1985 | |||
l The licensee stated that the startup test surveillances are | |||
considered to be complete when the last step is complete which | |||
, is prior to the test evaluation section writeup, but these | |||
surveillances were not signed and dated until after the test | |||
: | |||
evaluation was complete. | |||
During discussions with the licensee, the licensee stated their | |||
intent to review the startup test procedures and revise them as | |||
i | |||
necessary to provide for signatures and dates that would signify | |||
completion of the tests to the extent necessary to satisfy | |||
L surveillance requirements prior to proceeding with a reactor | |||
startup. This is an open item (295/85027-04) pending procedure | |||
revisions and subsequent NRC review. | |||
b. With regard to TSS 15.6.57, " Checkout of the Bank Overlap Unit," the | |||
inspector noted the following: | |||
l (1) Step 7.5.2 stated, "All rod positioning indicators are reading | |||
zero steps." When this step was signed, however, some of the | |||
Rod Positioning Indicators (RPI) were not reading zero as | |||
documented in the Data Sheet Section. For example, for | |||
Shutdown Bank A the following values were recorded: | |||
Rod Designation (Group) RPI Recorded Steps | |||
M2(2) l 5 | |||
l D2(1) l -5 | |||
j P4(1) l 5 | |||
t B4(2) l 0 | |||
P12(2) l 0 | |||
l | |||
B12(1) l 0 | |||
M14(1) l 5 | |||
D14(2) l 7 | |||
During discussions between the inspector and the licensee, | |||
the licensee indicated that: | |||
(a) This test was performed prior to the RPIs being | |||
calibrated (that is, prior to TSS 15.6.26 being | |||
performed) anJ, therefore, a precaution statement | |||
should have been included in the procedure to state | |||
that the RPI signals are not valid prior to | |||
7 | |||
. | |||
. | |||
TSS 15.6.26 being completed. (The procedure | |||
contained precaution 5.6 which stated, "If this | |||
test is performed in cold shutdown, the RPI signals | |||
are not valid since they are calibrated for hot | |||
shutdown conditions." This precaution did not | |||
apply to TSS 15.6.57 as performed on June 11,1985, | |||
because it was performed at hot shutdown conditions.) | |||
(b) The intent of Step 7.5.2 was for the RPIs to read | |||
within a tolerance band of zero steps. | |||
The licensee initiated a procedure change request on | |||
August 15, 1985, to include the precaution and tolerance | |||
band discussed above. | |||
(2) The test evaluation section stated, "Several of the rod | |||
bottom lights did not clear at 20 steps which is acceptable | |||
since the RPI calibration had not yet been performed." The | |||
Precautions, Limitations and Setpoint document establishes | |||
20 steps as the setpoint for the rod bottom bistables. Upon | |||
the inspector's request to review the documentation that showed | |||
that the rod bottom lights had cleared at 20 steps (following | |||
the RPI calibration), the licensee responded that the check | |||
was made but was not documented. In discussions with the | |||
licensee, the Station Nuclear Engineer stated that the station | |||
procedures would be modified to include a check that the rod | |||
bottom lights go out at 20 steps during the initial startup | |||
following a refueling. This is an open item (295/85027-05) | |||
pending the procedure revision and subsequent NRC review. | |||
No violations or deviations were identified. However, portions of | |||
this area require further review and evaluation and are considered | |||
to be open items. | |||
7. Incore/Excore Detector Calibration | |||
For Unit 1 Cycle 9, the inspector reviewed licensee procedures to verify | |||
that prerequisites, precautions and plant conditions were met, that | |||
results were within acceptance criteria and consistent with Technical | |||
Specifications and that any discrepancies were properly evaluated. The | |||
inspector utilized the following procedures during the review: | |||
* TSS 15.6.2, "NIS Calibration," dated March 1, 1985, | |||
and performed for Unit 1 Cycle 9 on July 3, 1985. | |||
* TSS 15.6,0, " Flux Map Data Acquisition, Power | |||
Distribution and Incore/Excore Axial Imbalance Checks," | |||
dated January 12, 1984, and performed for Unit 1 | |||
Cycle 9 on: | |||
July 2, 1985 (associated with Flux Map 1-9-06) | |||
July 3, 1985 (associated with Flux Map 1-9-07) | |||
8 | |||
- - . | |||
. | |||
= - - | |||
. | |||
. | |||
July 3, 1985 (associated with Flux Map 1-9-08) | |||
During the review, the inspector noted that surveillance test TSS 15.6.2, | |||
"NIS Calibration," was required to be completed prior to exceeding 90% | |||
power per Technical Specification 3.2.2.C.1. However, tne signatures in | |||
the last section of the procedure (the test results evaluation section) | |||
were as follows: | |||
Unit 1 exceeded 90% power, July 5,1985 | |||
Test Engineer's Signature, July 8, 1985 | |||
Station Nuclear Engineer's Signature, July 10, 1985 | |||
Technical Staff Supervisor's Signature, July 19, 1985 | |||
This is another example of the situation discussed in Paragraph 6.a.(3) | |||
of this inspection report. Refer to Paragraph 6.a(3) for additional | |||
discussion. | |||
The inspector reviewed the following procedures performed during | |||
Unit 1 Cycle 8 to verify that Technical Specification 3.2.2.C.1, | |||
concerning periodic checks and recalibrations of the excore nuclear | |||
detectors, was being met. | |||
* TSS 15.6.2, "NIS Calibration," performed for Unit 1 | |||
Cycle 8 on the following dates: | |||
February 18, 1984 | |||
May 15, 1984 | |||
September 10, 1984 | |||
December 15, 1984 | |||
* TSS 15.6.0, " Flux Map Data Acquisition Power Distribution | |||
and Incore/Excore Imbalance Checks," performed 29 times for | |||
Unit 1 Cycle 8 between February 11, 1984 and December 28, | |||
1984, inclusive. | |||
No violations or deviations were identified. | |||
8. Open Items | |||
Open items are matters which have been dis:ussed with the licensee, which | |||
will be reviewed further by the inspector, oi1 which involve some action | |||
on the part of the NRC or licensee or both. Lpen items disclosed during | |||
the inspection are discussed in Paragraphs 3, 4, 6.a.(3), and 6.b.(2). | |||
9. Unresolved Items | |||
Unresolved items are matters about which more information is required | |||
in order to ascertain whether they are acceptable items, items of | |||
noncompliance, or deviations. An unresolved item disclosed during | |||
the inspection is discussed in Paragraph 5. | |||
9 | |||
.- | |||
.. | |||
10. Exit Interview | |||
- The inspector met with licensee representatives denoted in Paragraph 1 at | |||
the conclusion of.the inspection on August 30, 1985. The inspector | |||
summarized the scope of the inspection and the findings. The inspector | |||
- | |||
.al so discussed the likely informational content of the inspection report | |||
with regard to documents or processes reviewed by the inspector during | |||
the inspection. The licensee did not identify any such | |||
documents / processes as proprietary. | |||
?, | |||
10 | |||
t- | |||
}} |
Revision as of 04:56, 23 July 2020
ML20132C589 | |
Person / Time | |
---|---|
Site: | Zion File:ZionSolutions icon.png |
Issue date: | 09/20/1985 |
From: | Mccormickbarge, Ring M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
To: | |
Shared Package | |
ML20132C583 | List: |
References | |
50-295-85-27, 50-304-85-28, NUDOCS 8509270095 | |
Download: ML20132C589 (10) | |
See also: IR 05000722/2008030
Text
.
-U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report Nos. 50-295/85027(CRS); 50-304/85028(DRS)
Docket Nos. 50-295; 50-304 License Nos. DPR-39; DPR-48
Licensee: Commonwealth Edison Company
.P. O. Box 767
Chicago, Illinois 60690
Facility Name: Zion Nuclear Power Station, Units 1 and 2
Inspection At: Zion, Illinois
Inspection Conducted: July 22 through Auge t 30. 1985
IfM.}l.d Y Dtd d' M
Inspector: bcCormick-Barger b28- h5
Date
3 _
0 S 9 ()V
Approved By: M. A. Ring, Chief
Test Programs Section Date
Inspection Summary
Inspection on July 22 through August 30, 1985 (Report No. 50-295/85027(DRS);
50-304/85028(DRS))
Areas Inspected: Routine, announced inspection of licensee actions on
previous inspection findings, general program requirements for Unit 1
Cycle 9 Startup Testing, reactor thermocouple /RTD cross calibration,
isothermal temperature coefficient measurement, doppler coefficient
measurement, control rod drive and rod position indication checks, and
incore/excore calibration. The inspection involved 94 inspector-hours
onsite.
Results: No violations or deviations were identified.
0
8509270095
ADOCK
850 295
G
_ _ _ _ _ _ _ _ _ _
.
.
DETAILS
1. Persons Contacted
- K. Graesser, Station Manager
- T. Rieck, Station Superintendent, Services
- W. Kurth, Assistant Superintendent, Services
- C. Schultz, Assistant Technical Staff Supervisor
- R. Chin, Nuclear Group Leader
- W. Stone, Quality Assurance Supervisor
- J. Ballard, Quality Control Supervisor
Additional station technical and administrative personnel were
contacted by the inspector during the course of the inspection.
- Denotes those personnel present at the exit interview.
2. Licensee Action on Previous Inspection Findings
(Closed) Open Item (295/82-21-01): This item involved two concerns -
the lack of acceptance criteria for the wide range Resistance Temperature
Detectors (RTD) in surveillance procedure TSS 15.6.72, "RTD Cross
Calibration," dated November 10, 1981 and that 15 of the 65 incore
thermocouples for Unit 1 Cycle 7 were inoperable.
The inspector reviewed TSS 15.6.72, "RTD Cross Calibration," dated
September 20, 1984, and noted that it contained the following acceptance
criterion for the wide range RTDs: " Step 6.13. Evaluate the wide range
RTDs using the following acceptance criterion: -6 F 1 (predicted wide
range RTD temperature - average temperature of all the good narrow range
RTDs) 5 0.5 F." A review of the incore thermocouples for operability
based on the results of TSS 15.6.72, dated September 20, 1984, and
performed for Unit 1 Cycle 9 on September 7-13, 1985, indicated that
only 5 of 65 incore thermocouples were inoperable which the inspector
cormiders acceptable.
3. General Program Requirements for Unit 1 Cycle 9 Startup Testing
The inspector utilized the following documents during a review of
general program requirements for Unit 1 Cycle 9 Startup Testing:
- Reload Safety Evaluation Zion Nuclear Plant, Unit 1
Cycle 9, July 1984.
- NRC letter J. Norris to D. L. Farrar, NRC transmittal
of Technical Specification Amendments No. 89 to DPR-39
and No. 79 to DPR-48 and the associated safety evaluation 1
'
report, dated May 24, 1985.
2
. _ _ _ _ _ - _ - _ _
.
.
- Commonwealth Edison (CECO) Internal Memorandum,
H. E. Bliss, Nuclear Fuel Services Manager, to
K. L. Graesser, Zion Station Manger, " Zion 1 Cycle 9
CAOC Analysis Based on Actual E0C8 Burnup," Z1C9/043,
dated June 7, 1985.
- Safety Parameter Interaction List for Zion, Unit 1
Cycle 9, approved January 4,1984.
- Zion 1, Cycle 9, Nuclear Design Report, NFSR-0035,
Revision 0.
l
- CECO memo, H. E. Bliss to K. L. Graesser, " Revision
to Table 7.2 of Zion, Unit 1 Cycle 9 Nuclear Design
Report," dated August 2, 1985.
'
- CECO memo, H. E. Bliss to K. L. Graesser, " Zion 1
Cycle 9 Rod Exchange Data," Z1C9/040, dated May 9, 1985.
- Technical Staff Surveillance (TSS) Procedure 15.6.51,
"Zero Power Physics Measurements Following Refueling,"
dated June 3, 1985 and performed for Unit 1 Cycle 9
on June 14-16, 1985.
- TSS Procedure 15.6.61, "At Power Physics Measurements
Following Refueling," dated January 10, 1984, and
performed for Unit 1 Cycle 9 on June 21, 1985
to July 27, 1985.
With regard to TSS 15.6.51, "Zero Power Physics Measurements Following '
Refueling," the results evaluation discussed inconsistencies in boron
sample measurements taken during startup physics testing. Boron sample
measurement inconsistencies were also identified in the results
evaluation for TSS 15.6.51, dated July 2, 1984, and performed for Unit 2,
Cycle 8 on July 4-7, 1984. For Unit 1 Cycle 9, differences between two
measurements of the same boron sample were as much as 67 ppm and,
for Unit 2 Cycle 8, were as much as 45 ppm. The corrective actions
discussed in the Unit 2 Cycle 8 test evaluation recommended that a
meeting be held between the Nuclear Group and the station chemists to
discuss the importance of boron sampling measurements. Although no
meeting minutes were kept, the Station Nuclear Engineer stated that
this meeting had taken place prior to the Unit 1 Cycle 9 startup. To
calibrate the boron measurement instrumentation, a standard with known
boron concentration is used. In an attempt to improve boron sample
measurements, the Unit 1 Cycle 9 test evaluation indicated that the
licensee intends to investigate the possibility of using a standard
with a boron concentration nearer to the boron concentration of the
samples being measured. Review of the licensee's corrective actions
in a subsequent NRC inspection will be tracked as an open item
I
L
(295/85027-01).
I
.s
3
i
k . .
.
.
. . . . _ _ - _ _ _ _ _ - _ - _ _ _ -
TSS 15.6.51 and TSS 15.6.61 both contained steps requiring that the
manufacturer, model and serial number of all instruments used in the
reactivity computer system be recorded. In both cases, the inspector was
unable to locate this information in the completed test packages. In
discussions of this matter with the licensee, the licensee explained
that, since Zion has only one reactivity computer system, a standard
type written sheet had been developed which provided all of this
information. This sheet was inadvertently omitted from the completed
test packages. The licensee stated their intent to take the necessary
actions to ensure that future test packages include reactivity computer
system data as required.
Paragraph 5.a of this report contains comments regarding the Zion 1
Cycle 9 Nuclear Design Report and CECO memo, " Revision to Table 7.2 of
Zion, Unit 1 Cycle 9 Nuclear Design Report," dated August 2, 1985.
No violations or deviations were identified. However, a portion of this
area requires further review and evaluation and is considered to be an
open item.
4. Reactor Thermocouple /RTD Cross Calibration
The inspector reviewed surveillance procedure TSS 15.6.72, "RTD Cross
Calibration," dated September 20, 1984, and performed for Unit 1 Cycle 9
on June 7-13, 1985, to determine that results obtained were within
prescribed limits and that any discrepancies were properly evaluated.
During this review the inspector noted that the results for one of the
wide range RTDs did not meet the acceptance criterion for wide range RTDs
of: "-6 F <_ (predicted wide range RTD temperature minus the average
temperature of all the good narrow range RTDs) < 0.5 F." The licensee
stated that an evaluation of this condition tooE place prior to proceeding
with the Unit 1 Cycle 9 initial startup. The inspector had no evidence
that would contradict that statement. However, the documented evaluation
was not signed until June 27, 1985. (The test which was required to be
performed prior to initial criticality was performed on June 12-13, 1985, ,
initial criticality occurred on June 14, 1985, and Unit 1 was at 88% power
'
on June 25, 1985.) In discussions with the licensee concerning this
matter, the licensee agreed that, in the future, the evaluation of a
startup test acceptance criterion that was not satisfied would be
documented prior to proceeding with the startup testing. This is an
open item pending NRC review during the next core physics startup
testing inspection (295/85027-02).
No violations or deviations were identified. However, a portion of this
area requires further review and evaluation and is considered to be an ,
open item. )
5. Isothermal Temperature Coefficient and Doppler Coefficient
The inspector reviewed licensee procedures and results to verify that
prerequisites, precautions and plant conditions were met, that results
4
were within acceptance criteria and consistent with Technical
Specifications and that any discrepancies were properly evaluated.
The inspector utilized the following procedures during the review:
- TSS 15.6.54, " Isothermal Moderator Temperature Coefficient
Measurements," dated May 27, 1982, and performed for Unit 1
Cycle 9 on June 15, 1985.
- TSS 15.6.62, " Moderator Temperature Coefficient Measurement,"
dated July 9, 1980, (with Station Procedure Change Request
A85-613 approved June 27, 1985, attached) and performed for
Unit 1 Cycle 9 on July 9, 1985.
- TSS 15.6.62, " Moderator Temperature Coefficient Measurement,"
dated July 9,1980, (with Station Procedure Change Request
A85-613 approved June 27, 1985, attached) and performed for
Unit 1 Cycle 9 on July 27, 1985.
- TSS 15.6.63, " Doppler Coefficient Measurement," dated
February 8, 1985, (with Station Procedure Change Request
A85-612 approved June 27, 1985, attached) and performed for
Unit 1 Cycle 9 on July 9, 1985.
- TSS 15.6.63, " Doppler Coefficient Measurement," dated
February 8, 1985, (with Station Procedure Change Request
A85-612 approved June 27, 1985, attached) and performed for
Unit 1 Cycle 9 on July 22, 1985.
The inspector also utilized the following document during the review:
- " Nuclear Design Report for Zion, Unit 1 Cycle 9," NFSR 0035,
Revision 0, Nuclear Fuel Services - Commonwealth Edison Company,
dated April 1985.
a. During the test evaluation for TSS 15.6.54, " Isothermal Moderator
Temperature Coefficient Measurements," performed on June 15, 1985, a
member of the Technical Staff discovered an apparent error in
Table 7.2 of the Nuclear Design Report. In discussions between the
Technical Staff and the Nuclear Fuel Services Section, it was
confirmed that an error existed in the method used to generate the
moderator temperature coefficient component of the isothermal
temperature coefficient reported in Table 7.2. Table 7.2 was
subsequently corrected via a memo from H. E. Bliss, Nuclear
Fuel Services Manager, to K. L. Graesser, Zion Station Manager,
" Revision to Table 7.2 of Zion, Unit 1 Cycle 9 Nuclear Design
Report," Z1C9/045, dated August 2, 1985. Other than this memo,
members of the Technical Staff were not cognizant of corrective i
actions taken by the Nuclear Fuel Services section. Therefore, l
pending an NRC inspection of the CECO Nuclear Fuel Services section l
to review the licensee's corrective actions to prevent recurrence l
of errors in nuclear design reports, this is considered an unresolved
item (295/85027-03).
5
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1
--
- _ _ _ - . - - - - - - - - - - - - - _ _ _ _ ,
.
b. The test evaluation for TSS 15.6.63, " Doppler Coefficient
Measurement," performed on July 9, 1985, stated that all design
and safety criteria were met. However, the measured doppler
coefficient was -7.59 pcm/% power which was outside of the design
acceptance criterion band of -8.95 1.34 pcm/% power (i.e.,
-7.61 to -10.29 pcm/% power). At the time that the inspector
reviewed the test evaluation, the Technical Staff Supervisor had
not signed the procedure yet. Additionally, a subsequent doppler
coefficient measurement had been performed on July 22, 1985, which
resulted in a doppler coefficient value that did meet the design l
acceptance criterion. Following discussion of this matter with the '
licensee, the licensee rewrote the test evaluation to reflect the
fact that the design acceptance criterion for the doppler coefficient
had not been met in the July 9 instance.
No violations or deviations were identified. However, a portion of this
area requires further review and evaluation and is considered to be an
l unresolved item.
6. Control Rod Drive and Rod Position Indication Checks
i
f The inspector reviewed licensee procedures and results to verify that
} prerequisites, precautions and plant conditions were met, that results i
l' were within acceptance criteria and consistent with Technical l
Specifications and that any discrepancies were properly evaluated.
The inspector utilized the following procedures during the review:
- TSS 15.6.26, " Control Rod System Checkout," dated
January 1, 1985, and performed for Unit 1 Cycle 9
on June 10-12, 1985.
- TSS 15.6.57, "Checkcut of the Bank Overlap Unit,"
dated March 12, 1984, and performed for %it 1
Cycle 9 on June 11, 1985.
a. With regard to TSS 15.6.26, " Control Rod System Checkout,"
the inspector noted the following:
(1) All rod drop times satisfied the acceptance criterion
of 2.4 seconds or less required by the Technical
Specifications.
(2) The inspector reviewed the slave cycler strip chart traces
for power cabinets 180 and 1AC and the rod drop timing traces
for rods in Shutdown Banks A, C, and D, and Control Bank A.
The inspector had no cor,cerns as a result of the review of
these strip charts.
(3) Surveillance test TSS 15.6.26 was required to be completed
prior to initial criticality per Technical Specification 3/4.2.3.C.
However, the signatures in the last section of the procedure
(the test results evaluation section) were as follows:
6
.
.
!
Initial Criticality, June 14, 1985
Test Engineer's Signature, June 21, 1935
(Reactor at approximately 49% power)
l Station Nuclear Engineer's Signature, July 10, 1985
!
(Reactor at approximately 100% power)
Technical Staff Supervisor's Signature, July 19, 1985
l The licensee stated that the startup test surveillances are
considered to be complete when the last step is complete which
, is prior to the test evaluation section writeup, but these
surveillances were not signed and dated until after the test
evaluation was complete.
During discussions with the licensee, the licensee stated their
intent to review the startup test procedures and revise them as
i
necessary to provide for signatures and dates that would signify
completion of the tests to the extent necessary to satisfy
L surveillance requirements prior to proceeding with a reactor
startup. This is an open item (295/85027-04) pending procedure
revisions and subsequent NRC review.
b. With regard to TSS 15.6.57, " Checkout of the Bank Overlap Unit," the
inspector noted the following:
l (1) Step 7.5.2 stated, "All rod positioning indicators are reading
zero steps." When this step was signed, however, some of the
Rod Positioning Indicators (RPI) were not reading zero as
documented in the Data Sheet Section. For example, for
Shutdown Bank A the following values were recorded:
Rod Designation (Group) RPI Recorded Steps
M2(2) l 5
l D2(1) l -5
j P4(1) l 5
t B4(2) l 0
P12(2) l 0
l
B12(1) l 0
M14(1) l 5
D14(2) l 7
During discussions between the inspector and the licensee,
the licensee indicated that:
(a) This test was performed prior to the RPIs being
calibrated (that is, prior to TSS 15.6.26 being
performed) anJ, therefore, a precaution statement
should have been included in the procedure to state
that the RPI signals are not valid prior to
7
.
.
TSS 15.6.26 being completed. (The procedure
contained precaution 5.6 which stated, "If this
test is performed in cold shutdown, the RPI signals
are not valid since they are calibrated for hot
shutdown conditions." This precaution did not
apply to TSS 15.6.57 as performed on June 11,1985,
because it was performed at hot shutdown conditions.)
(b) The intent of Step 7.5.2 was for the RPIs to read
within a tolerance band of zero steps.
The licensee initiated a procedure change request on
August 15, 1985, to include the precaution and tolerance
band discussed above.
(2) The test evaluation section stated, "Several of the rod
bottom lights did not clear at 20 steps which is acceptable
since the RPI calibration had not yet been performed." The
Precautions, Limitations and Setpoint document establishes
20 steps as the setpoint for the rod bottom bistables. Upon
the inspector's request to review the documentation that showed
that the rod bottom lights had cleared at 20 steps (following
the RPI calibration), the licensee responded that the check
was made but was not documented. In discussions with the
licensee, the Station Nuclear Engineer stated that the station
procedures would be modified to include a check that the rod
bottom lights go out at 20 steps during the initial startup
following a refueling. This is an open item (295/85027-05)
pending the procedure revision and subsequent NRC review.
No violations or deviations were identified. However, portions of
this area require further review and evaluation and are considered
to be open items.
7. Incore/Excore Detector Calibration
For Unit 1 Cycle 9, the inspector reviewed licensee procedures to verify
that prerequisites, precautions and plant conditions were met, that
results were within acceptance criteria and consistent with Technical
Specifications and that any discrepancies were properly evaluated. The
inspector utilized the following procedures during the review:
- TSS 15.6.2, "NIS Calibration," dated March 1, 1985,
and performed for Unit 1 Cycle 9 on July 3, 1985.
- TSS 15.6,0, " Flux Map Data Acquisition, Power
Distribution and Incore/Excore Axial Imbalance Checks,"
dated January 12, 1984, and performed for Unit 1
Cycle 9 on:
July 2, 1985 (associated with Flux Map 1-9-06)
July 3, 1985 (associated with Flux Map 1-9-07)
8
- - .
.
= - -
.
.
July 3, 1985 (associated with Flux Map 1-9-08)
During the review, the inspector noted that surveillance test TSS 15.6.2,
"NIS Calibration," was required to be completed prior to exceeding 90%
power per Technical Specification 3.2.2.C.1. However, tne signatures in
the last section of the procedure (the test results evaluation section)
were as follows:
Unit 1 exceeded 90% power, July 5,1985
Test Engineer's Signature, July 8, 1985
Station Nuclear Engineer's Signature, July 10, 1985
Technical Staff Supervisor's Signature, July 19, 1985
This is another example of the situation discussed in Paragraph 6.a.(3)
of this inspection report. Refer to Paragraph 6.a(3) for additional
discussion.
The inspector reviewed the following procedures performed during
Unit 1 Cycle 8 to verify that Technical Specification 3.2.2.C.1,
concerning periodic checks and recalibrations of the excore nuclear
detectors, was being met.
- TSS 15.6.2, "NIS Calibration," performed for Unit 1
Cycle 8 on the following dates:
February 18, 1984
May 15, 1984
September 10, 1984
December 15, 1984
- TSS 15.6.0, " Flux Map Data Acquisition Power Distribution
and Incore/Excore Imbalance Checks," performed 29 times for
Unit 1 Cycle 8 between February 11, 1984 and December 28,
1984, inclusive.
No violations or deviations were identified.
8. Open Items
Open items are matters which have been dis:ussed with the licensee, which
will be reviewed further by the inspector, oi1 which involve some action
on the part of the NRC or licensee or both. Lpen items disclosed during
the inspection are discussed in Paragraphs 3, 4, 6.a.(3), and 6.b.(2).
9. Unresolved Items
Unresolved items are matters about which more information is required
in order to ascertain whether they are acceptable items, items of
noncompliance, or deviations. An unresolved item disclosed during
the inspection is discussed in Paragraph 5.
9
.-
..
10. Exit Interview
- The inspector met with licensee representatives denoted in Paragraph 1 at
the conclusion of.the inspection on August 30, 1985. The inspector
summarized the scope of the inspection and the findings. The inspector
-
.al so discussed the likely informational content of the inspection report
with regard to documents or processes reviewed by the inspector during
the inspection. The licensee did not identify any such
documents / processes as proprietary.
?,
10
t-