IR 05000302/1975001
| ML19319C734 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 01/30/1975 |
| From: | Jape F, Robert Lewis, Whitt K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C730 | List: |
| References | |
| 50-302-75-01, 50-302-75-1, NUDOCS 8003030850 | |
| Download: ML19319C734 (12) | |
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UNITED STATES
'v NUCLEAR REGULATORY COMMISSION fi REGION il 230 PE ACHTR EE STR EET. N. W. SulTE 888 N
ATLANTA GEORGI A 30303
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IE Inspection Report No. 50-302/75-1
Licensee:
Florida Power Corporation
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3201 34th Street, South P. O. Box 14042
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St. Petersburg, Florida 33733 Facility Name: Crystal River 3
Docket No.:
50-302
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License No. :
CPPR-51 Category:
B1 Location:
Crystal River, Florida Type of License: B&W, PWR, 2452 Mwt Type of Inspection:
Routine, Unannounced b
Dates of Inspection: January 14-17, 1975
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Dates of Previous Inspection: October 1-4, 1974 Principal Inspector:
K. W. Whitt, Reactor Inspector Facilities Section Facilities Test and Startup Branch Accompanying Inspector:
F. Jape, Reactor !nspector Facilities Section Facilities Test and Startup Branch Other Accompanying Personne -
None d
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Principal Inspector:
A ft< t
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l K. W/ Whitt, 'Reacto ns/ector
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Date Facilities Sectio V
Facilities Test and Startup Branch i
Reviewed by:
M'd'
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R. C. Lewis, Senior Reactor Inspector Date Facilities Section h 'ilities Test and Startup Branch gTIO4 PD3_.l
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DOPY SENT TO:
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- '78 6 *
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8003030
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IE Rpt. No. 50-302/75-1-2-
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SUMMARY OF FINDINGS
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I.
Enforcement Matters
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j There were no items of noncompliance iden"ified during the inspection.
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II.
Licensee Action on Previously Identified Enforcement Matters
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There were no previously identified enforcement matters requiring resolution.
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III. New Unresolved Items
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75-1/1 Deficiency in ITE Molded Case Circuit Bre. 'ers, Type HE-3 (ROB 74-8) l
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Replacement of 52 ITE Breakers was accomplished through the
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mechanism of an engineering change notice (ECN).
The ECN j
review and approval method was inadaquate.
(Details I, paragraph 2)
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75-1/2 Preoperational Test Procedure Review
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Corunts resulting from the review of eight preoperationsi
test procedures have not been resolved.
(Details II, l
paragraph 3)
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75-1/3 Test Results Review
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l Conments resulting from the review of the results of two tests I
have not been resolved.
(Details I, paragraph 8 and Details II, paragraph O
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IV.
Status of Previou identified Unresolved Items
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73-12/1 Preopert.onal Test Program Controls
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The necessary changes to the Transition Control Procedure and the Temporary Test Device Control Procedure have been incorporated in Revision 5 of the Test Program Guide which was approved on October 24, 1974. This item is closed.
(Details I, paragraph 6)
74-11/1 Operational Procedures This item was not inspected.
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l IE Rpt. No. 50-302/75-1-3-w l
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74-11/2 Loose Parts Monitoring
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A proposed change to the FSAR regarding loose parts monitoring'
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has been incorporated.in Amendment 44, but the amendment has i
not been submitted to the NRC.
(Details I, paragraph 7)
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j V.
1% usual Occurrences I
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None
l VI.
Other Significant Findings
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A.
Incorrect Coils in Westinghouse Type SC Relays ~ (ROB 74-12)
FPC has determined that relays of this type are not used at CR-3.,
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l This item is closed.
(Details I, paragraph 3)
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B.
Improper Factory Wiring on General Electric Motor Control Centers
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i (ROB 74-13)
I The licensee has determined that wiring of this type is not used
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in breaker starters at CR-3.
This item is closed.
(Details I, l.
paragraph 4)
C.
Misapplication of Cuttler-Hammer Three Position Maintained Switch Model No.10250T (ROB-74-15)
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l The licensee has determined that switches of this type are not used at CR-3.
This item is closed.
(Details I, paragraph 5)
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D.
Resolution of Comments on Preoperational Test Procedures The preoperational test procedure review comments reported in RO Report No. 50-302/74-9, Details II, paragraph 4, have been i,
resolved. This item is closed.
(Details II, paragraph 2)
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E.
Project Status 1.
General Construction was reported to be 95% complete. Testing of
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safety related systems has commenced.
The licensee reported i
that approximately 15.3% of the overall test program has been *
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coupleted. -The latest issue of the testing schedule indicates l
that hot functional testing and other preparations for fuel l
Toading will be completed by May 1976.
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IE Rpt. No. 50-302/75-1-4-
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2.
Test organization The seven groups of the testing organization under the Manager,
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Generation Testing, have been consolidated into fivs groups.
- The groups and the heads of the groups are as follows:
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Manager, Test Procedures - K. O. Vogel
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Administrative Manager - C. R. Pope Manager, Field Testing - G. Walker
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Scheduling Engineer - J. H. Reedy
Superintendent Testing, QC - J. H. Rinne
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The previous testing organization is outlined in RO Report No.
50-302/74-13, Summary Cection VI.A.2.
3.
Transition Status
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l A licensee representative stated that approximately 76% of the
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plant mechanical equipment and 69% of the plant electrical l
equipment had been turned over from construction to generation l
testing.
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4.
Procedure Status i
Number Number in Number Class, Identified Final Draft, Approved
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12
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II 104
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F.
Operation Organization and Personnel Changes
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FPC has recently established a Department of Power Production.
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l This new department is being directed by W. O. Stewart. One of
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the positions that reports to the Director, Power Production, is the Manager, Nuclear Operations. Mr. J. Alberdi, formally the CR-3 Plant Superintendent, has been assigned this position.
Mr. G. P. Beatty is now the CR-3 Plant Superintendent and reports to the Manager, Nuclear Operations. The position of General Superintendent has been abolished.
Mr. D. W. West, formerly the Chemical and Radiological Protection Engineer at CR-3, has been promoted to Plant Superintendent of a fossil plant. A new Chemical and Radiological Protection Engineer had not been selected for CR-3 at the conclusion of this inspection. A licensee I
representative stated that the FSAR would be amended to reflect the
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most recent organization and the key personnel changes.
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lE Rpt. No. 50-302/75-1-5-
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j VII. Management Interview e
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A management interview was held at the conclusion of the inspection on January 17, 1975. The following licensee personnel participated:
H. L. Bennett - Director, Generation Construc tion
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R. S. Burns - Engineering Manager i
E. E. Froats - Manager, Site Surveillance
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J. C. Hobbs, Jr. - Manager, Generation Testing
C. E. Jackson - Construction Superintendent R. W. Slater - Quality Engineer
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K. O. Vogel - Manager, Test Procedures
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A.
Discussed the Regulatory Operations Bulletins:
,t The inspector stated that ROB 74-8 would remain open and carried as an unresolved item until the action in regard to R0B 74-8 has been formally approved by the Director, Generation Engineering.
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A licensee representative stated that the action taken in regard to ROB 74-8 would be evaluated and the ECN review and approval process would be reviewed.
0 Details I, paragraphs 2, 3, 4, and 5)
B.
Discussed preoperational test status.
(Summary ^Section VI.E)
C.
Discussed unresolved item Nos. 73-12/1, and 74-11/2 (Details I, l
paragraphs 6 and 7).
D.
Discussed the review of preoperational test procedures.
(Details II, I
paragraphs 2 and 3)
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E.
Discussed tre review of the results of two completed tests. The inspectors and licensee representatives were in agreement regarding actions needed to improve documentation of test rescits.
(Details I, paragraph 8 and Details II, paragraph 4)
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IE Rpt. No. 50-302/75-1 I-1
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~7 I DETAILS I Prepared By:
K. W. Whitt, Rhactor Inspegf/r Date j
Facilities Section Facilities Test and Startup Branch
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Dates of Inspection: January 14-17, 1975
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Reviewed By:
[. d.
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R. C. Lewis,' Senior Inspector Date
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Facilities Section Facilities Test and Startup Branch
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1.
Individuals contacted i
Florida Power Corporation (FPC)
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G. F. Beatty - Plant Superintendent H. L. Bennett - Director, Generation Construction R. S. Burns - Engineering Manager E. E. Froats - Manager, Site Surveillance g' 's J. C. Hobbs, Jr. - Manager, Generation Testing (V)
C. E. Jackson - Construction Superintendent P. R. King - Quality Auditor R. W. Slater - Quality Engineer K. O. Vogel - Manager, Test Procedures
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2.
Deficiency in ITE Molded Case Circuit Breakers, Type EE-3 (ROB No. 74-8)
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This item was initially ' reported in R0 Report No. 50-302/74-10 and was transferred from the Facilities Construction Branch to the Facilities Test and Startup Branch in RO Report No. 50-302/74-15.
FPC informed Region II, by letter dated August 16, 1974, that ITE circuit breakers of the type described in R0B 74-8 were installed in two safety related areas. These areas were the 480 volt motor control centers and the A/C distribution panels. According to this letter, all the breakers in the 480 volt motor control centers had been tested by Allen-Bradley prior to their installation and FPC was in the process of determining the criteria used for the test and obtaining certification that all the breakers had been tested and accepted by Allen-Bradley. The breakers in the A/C distribution panels were being tested by EPC Power Test Department.
IIE Imperial Corporation informed FPC, by letter dated August 29, 1974, that the deficiencies in the ITE molded case circuit breakers, type HE-3, referenced in RDB 74-8, were related to only the thermal magnetic type breakers.
In a letter dated October 3, 1974, FPC informed Directorate of Regulatory Operations (DRO), Region II ('~'h that 52 of the thermo magnetic type breakers had been identified in
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safety related systems at CR-3.
The letter also stated that FPC had
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IE Ryt. No. 50-302/75-1 I-2 C'
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made the decision to replace the 52 identified thermo magnetic type breakers with ITE type HE-3 breakers which had been manuf actured-af ter May 1974 and certified by ITE that the trip elements follow the published curves for this type breaker.
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The 52 potentially defective circuit breakers have been replaced.
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The installation was reviewed during this inspection. An engineering
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change notice (ECN) was the mechanism used to initiate the replacement
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of the breakers. Section 13.2.7.2 of the Final Safety Analysis Report I
(FSAR) states, in part, that there shall be no field initiated design
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changes of any nature performed without approval of the Director,
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Generation Engineering, or authorized delegate.
Engineering procedure
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No.19, which provides implementing instructions for the requi,rements of quality assurance procedure No. 3.11, " Design Change Control",
j assigns ECN approval responsibility to the generation engineering engi-neer that is responsible for the design change. The ECN used to replace the ITE, Type HE-3 circuit breakers had the name of the initiator printed
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in the approval position. A review of other ECN's indicated that a
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printed name in the approval space'was the generally accepted method
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of approval. The inspector stated that he did not think that the in-
tent of the FSAR Comitment was being mat. The level of management
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approvr.1 specified by the FSAR appears reasonable for determining the
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merit's of design changes. While it is recognized that the director will not always be available to approve ECN's, better control is
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needed,'and the specific individual authorized to approve design changes should be delegated in writing. The irspector also stated that a printed name should not constitute approval, since anyone could print a name and there is no distinctive identifying quality in print-
ing.
l The inspector reviewed the certification provided by ITE Imperial i
Corporation and the documentation used in perfortaing the design change and had no questions except as outlined above. Also, a sample inspec-tion of the newly installed circuit breakers indicated that they had
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been manufactured after May 1974.
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The inspector stated that written documentation was not available that l
indicated that the Director, Generation Engineering had approved the action taken in the replacement of the affected circuit breakers
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(RDB 74-8).
In order to close out the unresolved item (75-1/1), a
' written description of the general method to be used for handling design changes, including the designation of an authorized delegate
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or delegates, was.necessary. At the management interview a management representative stated that the method of handling ECN's would be l
reviewed and appropriate action would be taken.
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IE Rpt. No. 50-302/75-1 I-3
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3.
Incorrect Coils in Westinghouse Type SG Relays (ROB 74-12)-
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FPC advised Region II by letter dated November 20, 1974, that Westinghouse
SG relays are not used at CR-3.
This item is closed.
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4.
Improper Factory Wiring on General Electric (GE) Motor Conr.71 Centers
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(RDB 74-13)
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FPC advised Region II by letter dated November 20, 1974, that GE Vulkene
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"600" cable type XHHW referenced in ROB 74-13 had not been used in
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breaker starters at CR-3.
This item is closed.
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Misapplication of Cutler-Hammer Three Position Maintained Switch
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Model No. 10250T (ROB 74-15)
By letter dated December 26, 1974, FPC has informed Region II 'that no
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Cutler-Hammer Switches of the type referenced in RDB 74-15 ar6 in use
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in any safety related systems at CR-3.
This item is closed.
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6.
Preoperational Test Program Controls This unresolved item (73-12/1) was initially reported in RO Report No. 50-302/73-12, Details I, paragraph 3, and subsequently discussed in R0 Report Nos. 74-2, 74-6, 74-9, and 74-11.
A complete revision of the Test Program Guide has been approved by FPC. This revision included the necessary changes to the Transition Control Procedure and the
l Temporary Test Device Procedure. This item is c~osed.
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Loose Parts Monitoring
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This unresolved item (74-11/2) was initially reported in RO Report No.
50-302/74-11, Details I, paragraph 5.
A change to Table 13.2 of the
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FS AR to delete the statement that the test program does not include a loose parts monitoring system for reactor internals has been incorporated in Amendment 44 to the FSAR. However, Amendment 44 had not been submitted to the Division of Reactor Licensing (DRL) at the conclusion of this inspeution. This item will remain open until Amendment 44 has been submitted to DRL.
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8.
Review of Test Results The results of one completed test were reviewed.
This test had been conducted in accordance with TP712661, " Decay Heat Sea Water System Hydro Test".
The test results had not gone through the FPC review process and had not been approved. The licensee's review and approval-s(
process will be reviewed during subsequent inspections.
The following
comments were discussed with a licensee representative. The incorpora-
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tion of the resolution of these comments in other test procedures will be reviewed during subsequent reviews of test results.
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IE Rpt. No. 50-302/75 1 I-4
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Comment 1: The test package did not contain drawings marked to, indicate
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-J the hydro ~
.e test boundries. The licensee representative stated that drawtugs were being " red lined" to indicate test boundries, but that the drawings for this test had not 'been placed in the official
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test package yet.
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Comment 2: The changes that had been made to the procedure during the
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performance of the test were not numbered. The licensee representative said that changes made to procedures in the future would be numbered.
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Comment 3: The test log appeared to have sufficient entries to deter-mine the major events that took place during the test, but some of the e
entries should be more definitive. The test log provided a space to record the date that the various events took place but no space was provided for the time and tioes were not recorded. The licensee represen-tative stated that a space for recording the time of occurrence of. the recorded events would be added to the test log and test personnel would be instructed to better identify the recorded events.
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IE Rpt. No. 50-302/75-1 II-l i
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DETAILS II Prepared by:
AM A
F. Jape, Reactor $6spp6 tor Date Facilities Section
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Facilities Test and Startup Branch Dates of Inspection: January 14-17, 1975
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Reviewed by: [. C.,._tA
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R. C. Lewis, Senior Inspector Date Facilities Section Facilities Test and Startup Branch
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Personnel Contacted R. W. Slater - Quality Engineer K. O. Vogel - Manager, Test Procedures J. C. Hobbs, Jr. - Manager, Generation Testing 2.
Preoperational Test Comments b
During a previous inspection E!a number of comments were identified concerning preoperational' test procedures. Followup on these comments was completed during this inspection and all items are closed. The pertinent comments have been incorporated into the standard format used for preparing test procedures an' in the administration of the test program.
3.
Review of Class I and Class II Test Procedures Eight preoperational test procedures were reviewed for technical content and format. The format of the test procedures was compared with that described in ANSI 18.7-1972, Part 6.2.5 and Regulatory Guide
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1.68, Appendi:: C.
The purpose or objective of the test was clearly stated and acceptance criteria were identified.
Step-by-step instruc-tions were presented to properly perform the test. The inspector had one consnent concerning the use of appropriate operating procedures
1l RO:II Inspection Report 50-302/74-9, Details II, paragraph 4
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IE Rpt. No. 50-302/75-1 II-2
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when conducting the test.
The licensee representative stated that
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operating procedures are planned to be incorporated in the test
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procedures and will be utilized whenever possible during the conduct
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of a test. This item will be reviewed during a subsequent inspection.
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Other comments of a minor nature were discussed and resolved with the
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licensee representative.
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The tests reviewed during this inspection were as follows:
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TP 7 1 171 11 1, Decay Heat Pumps Ventilation System Functional Test.
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TP 7 2 203 08 1, Borated Water Storage Tank Instrumentation Calibration.
TP 7 1 204 01 0, Reactor Building Spray System Hydrostatic Test.
- TP 7 1 204 03 0, Reactor Building Spray System Functional Test.
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TP 7 1 266 01 0, Decay Heat Sea. Water System Hydrostatic Test.
TP 7 1 266 03 0, Decay Heat Sea Water System Functional Test.
,_s TP 7 1 268 03 0, Decay Heat Closed Cycle Cooling System Functional
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Test.
TP 7 1411 16 0, ES Motor Control Centers Electrical and Functional Test.
4.
Review of Test Results The test results of TP 71204 05 0, " Reactor Building Ring and Riser Hydro and Air Blow Test," were examined by the inspector.
The test
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had been compleMd but the test results had not yet been reviewed and accepted at the time the inspector examined the records.
The Test
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Working Group Chairman advised the inspector that this test was scheduled for review in the very near future.
The inspector had several comments which were discussed and resolved with the licensee representatives. These are summarized below:
a.
In the package of records associated with the test, it was not obvious that all Engineering Change Notices, (ECN) had been taken into account.
The licensee stated that a search of all ECN's is
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made prior to conduct of a test and applicable ECN's are included in the record file. Also, that in the future, a list of all ECN's that apply will be included in the record file.
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b.
The inspector noted that there were six minor revisions, one '
major revision and two deviations made to this test, and that they were not serially identified in any manner to ensure continuity of the record.
The licensee stated that a method would be adopted to maintain control of procedural changes t
made during conduct of a test.
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c.
During the conduct of the test, a test deficiency was identified.
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The record reflects that the deficiency will be resolved during
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the performance of the reactor building spray system test.
There does not appear to be any formal method to require that
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this deficiency be added to the other test. The licensee
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representative acknowledged that this could be a tracking problem and stated that a method would be established to keep track of these items.
The licensee's method for evaluating test results would be examined during a subsequent inspection.
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