IR 05000302/1974006
| ML19319C940 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/29/1974 |
| From: | Robert Lewis, Whitt K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19319C933 | List: |
| References | |
| 50-302-74-06, 50-302-74-6, NUDOCS 8003040881 | |
| Download: ML19319C940 (11) | |
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ATOMIC ENERGY COMMISSION
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RO Inspection Report No. 50-302/74-6
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Licensee: Florida Power Corporation
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3201 34th Street, South P. O. Box 14042
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St. Petersburg, Florida 33733
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Facility Neme:
Crystal River 3 Docket No.:
50-202
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License No.:
CPPR-51 Category:
B1
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Location: Crystal River, Florida Type of License:
B&W, PWR, 2452 Mwe Type of Inspection: Routine, Unannounced Dates of Inspection; March 26-29, 1974 Dates of Previous Inspection: January 30-31, 1974 and February 1, 1974 Principal Inspector:
K. W. Whitt, Reactor Inspector Facilities Test and Startup Branch Accompanying Inspector: None Other Accompanying Personnel: None eb
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Principal Y pector:
K. W. Whitt, Reacfor Inspectoy/ //
Date Facilities Test and Startup Branch Reviewed By:
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R. C. Lewis, Acting Chief /
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Facilities Test and Startup Branch--- g JISIC
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8008040
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Ro Rpt. No. 50-302/74-6-2-
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SuefARY OF FINDINGS
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I.
Enforcement Matters
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A.
Violations
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None o.
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B.
Safety Items
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C None
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II.
Licensee Action on Previously Identified Enforcement Matters
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None identified.
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III. New Unresolved Items
~74-6/1 Containment Building Integrity Information regarding measures taken to maintain containment
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integrity while the refueling canal is being drained was requested and obtained. This item is considered closed.
(Details, paragraph 2)
74-6/2 PWR Main Steam Line Isolation Valves Information was requested to permit the evaluation of the
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extent of a possible generic problem related to the failure of a number of main steam line isolation valves at various PWR facilities.
The requested information has been provided.
This item is considered closed.
(Details, paragraph 10)
IV.
Status of Previously Identified Unresolved Items 73-10/1 Preoperational Environmental Monitoring Progran
This item was not inspected.
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73-12/1 Preonerational Test Program Controls The Transition Control Procedure and the Temporary Test Device
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Control Procedure have been approved.
Copies of these documents were provided to the inspector at the management interview; but i
they have not been reviewed.
(Details, paragraph 3)
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Q RO Rpt. No. 50-302/74-6-3-
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73-12/2 Steam Generator and Prescurizer Safety Valves
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The licensee has stated intentions to bench' test the steam generator and pressurizer safety valves. The valves will be.
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tested in accordance with appropriate approved test procedures.
This item is considered closed.
(Details, paragraph 7)
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i V.
Unusual Occurrences
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None i
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VI.
Other Significant Findings
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- Proiect Status There has been no significant change in the status of testing s'ince i
the last inspect. ion. No safety related systems have been turned over to the power testing group in their entirety and no preoperational testing has been performed.
VII. Management Interview i
A management interview was held at the conclusion of the inspection on
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March 29, 1974. The following licensee personnel participated:
q Florida Power Corporation (FPC)
P. G. Davis, Jr. - Manager, Power Testing E. E. Proats - Manager, Nuclear Site Surveillance R. W. Slater - Site Quality Engineer J. Alberdi - Nuclear Plant Superintendent
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-u A.
New unresolved item 74-6/1, Containment Building Integrity was discussed.
(Details, paragraph 2).
B.
Previously identified unresolved items 73-12/1, "Preoperational Test Program Controls," and 73-12/2, " Steam Generator and Pressurizer Safety Valves," were discussed.
(Details, paragraph 3 and 7)
C.
The role of the Plant Review Committee in the review of test i
procedures was discussed.
(Details, paragraph 5)
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D.
The method of recording and changing test data was discussed.
(Details, paragraph 8)
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The method of control of' test procedure changes was d$scusseds
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. (Details, paragraph 9)
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The inspector stated that he had reviewed three generation quality and standards administrative instructions and had no comments.
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He said that he had no.further questions regarding the quality
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assurance program for testing at this time.
(Details,
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paragraph 4)
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The inspector stated that he had reviewed one test procedure and had discussed hir. conmients with a management member of power
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testing. He said that the comments had been resolved and that
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he understood the procedure would be revised. A licensee
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representative stated that this understanding was correct.
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.RO Rpt. No. 50-302/74-6-1-
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DETAILS.
Prepared by:
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K. W. Whitt, Reactair Inspector //
Date Facilities Test and Startup Bfanch
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Dates of Inspection: March 26-29,'1974
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Reviewed by:
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i R.. C. - Le.iis, 4 ting Chief
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Date Facilities Test and Startup Branch
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Personnel Contacted
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Florida Power Corporation (FPC)
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H. L. Bennett - Director, Generation Construction P. G. Davis, Jr. - Manager, Power Testing J. Alberdi - Nuclear Plant Superintendent P. F. McKee - Operations Engineer D. W. Pedrick - Compliance Engineer M. H. Klineman - Director, Generation Quality and Standards E. E. Froats - Manager, Nuclear Site Surveillance R. W. Slater - Site Quality Engineer'
J. B. Barrett - Engineer II, Generation Quality and Standards i
Gilbert Associates, Incorporated (GAI)
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J. D. Green - Testing QA Coordinator
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2.
Containment Building Integrity
The Crystal River 3 (CR-3) spent fuel pool is divided into two sections designated as "A" and "B".
The sections are separated by a permanent partition with a removable gate in the center which extends from the tcp of the pool down to a position 15 '8" above the pool floor.
Section
"A" is adjacent to the fuel transfer canal.
If 'the fuel transfer tube isolation valve was left open while. the refueling canal was being i
l drained, section "A" of the pool could be drained down to the bottom
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of the fuel transfer tube.
This would expose the upper half of any fuel elements stored in section "A".
If the gate was in position in the partition, section "B" would remain' filled.
If the gate was removed, section "B" could be drained down to the bottom of the gate -(15 '8" above th'e floor).
This would leave ' approximately ' three and one-half-feet'
of water over the top of the' fuel elements stored in section
"B".
The
. minimum water level in section "A" would be controlled by the elevation-
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RO Rpt.INo. 50-302/74-6-2-
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floor), and the minimum water level in section "B" would be controlled by the elevation of the bottom of the gate in the permanent partition
(assuring the' gate removed). _ Double isolation of the fuel trantfer
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tube is obtained by an isolation valve on the spent fuel pool side and a blind flange on the refueling canal side. Double isolation is
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verified by administrative controls utilizing operating procedures.
However, only single isolation is maintained during the draining of r
the refueling canal since the canal must be drained before the blind flange can be installed.
The refueling canal is drained by pumping
the water to the borated water storage tank (BWST).
An alarm sounds in the control room if the spent fuel pool water level in either
.l section "A"'or "B" drops twelve inches below a pre-established level.
There is also a spent fuel pool level indicator in the control room.
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The water from the refueling canal will almost fill the BWST.
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additional water from the spent fuel pool is' pumped to this tank, a l
high BWST level alarm will sound in the control room.
If the BWST overflows, the excess water will drain to the auxiliary building. sump.
When the auxiliary building sump pump starts on high sump level, an alarm sounds in the control room to indicate the possibility of excessive amounts of water being released. No further inspection i
effort is planned for this item.
3.
Preoperational Test Program Controls
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This unresolved item was initially discussed in RO Report No.
50-302/73-12, Details I, paragraph 3., Draft copies of the procedures
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for transition control and temporary test device control were provided to the inspector at the conclusion of the previous Facilities Test and Startup Branch inspection on February 1,1974.
These pro-cedures were reviewed and the following comments were submitted to a FPC management representative:
a.
Transition Control Procedure (Appendix 3 to the Test Program Guide (TPG)
The second sentence of Section 6.2 charges the Director, Generation Construction, with the responsibility for approving the transition.
The discussion of section 6.2 does not clearly define what transition is being discussed.
The transition being referenced could be the transition from construction to the power testing
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group or it could be the transition from the power testing
group to operations. The discussion of this section should be
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more clearly stated.
b.
Temporary Test Device Procedure (Appendix 5 to TPG)
(1) The procedure does not address lifted leads. Lifted leads end. jumpers should be controll'ed in a similar manner.
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RO Rpt. No. 50-302/74-6-3-
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(2) " Jumpers" and " temporary alteration tags" should be, defined.
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(3) The procedure should require all jumpers to be serially numbered.
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(4) No pr_eautions or limitations have been provided in. the
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pro. dure.
F (5) The method of jumper control has not been adequately described.
Step-by-step instructions for issuing, installing, removing
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and returning the jumpers and disconnect tags should be provided.
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(6) Section 6.1.1 is written to allow an individual to use a -
jumper continuously without tagging and recording each action.
If a jumper is attached so that it will remain in place without being held, it must be logged.
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(7) The procedure does not require a periodic audit of the i
temporary test device control system.
Such an audit by managerial personnel should be required.
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As a result of the procedure review by the various FPC groups (
and by the inspector, the procedares were rewritten.
The
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approved procedures were given to the inspector at the management interview. At this time, the licensee was advised that this item would remain open until the inspector had reviesed the approved procedures.
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QA Program for Testing
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This item was initially discussed in R0 Report No. 50-302/73-12, Details I, paragraph 4, and subsequently in RO Report No. 50-302/74-2.
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During this inspection, the inspector reviewed the three required generation quality and standards administrative instructions and had no comments. The instructions were:
a.
QOP 11.1, " Quality Program Surveillance of Transition From Construction to Test."
b.
QOP 11.2, " Quality Program Surveillance of Test Results Documentation."
c.
QOP 11.3, " Quality Program Surveillance of Test."
The inspector has no further questions concerning this item at c
this time.
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R0 Rpt. No. 50-302/74-6-4-
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5.
Role of Plant Review Comittee in the Review of Test Procedures The role of the Plant Review Comittee, in the review of test procedures,
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was discussed with members of plant operations and power testing.
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Agreement has been reached between these two groups regarding the test
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procedures to be reviewed by the Plant Review Comittee. The CR-3 FSAR requires that safety related test procedures be reviewed by the Plant Review Committee. A change is being initiated to the FSAR which will
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require the Plant Review Comittee to review only functional and operational safety related test procedures.
A licensee representative stated at the management interview that this change would be. submitted.
to'FPC management for approval by April 12, 1974.
All Class I and Class II (safety related) test procedures that go through the review and approval process before the FSAR change is approved will be re-viewed by the Plant Review Committee.
Subsequent to approval of the
FSAR change, Class I and Class II functional and operational test procedures will be reviewed by the Plant Review Committee. The TPC and the Plant Review Comittee charter will be revised as necessary
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to conform with the requirements of the FSAR after the change is
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approved.
6.
Test Procedure Review Test Procedure 7145122 0, "D. C. Power System Functional Test," was reviewed and the following comments were discussed with a licensee
representative:
Comment 1 Section 2.3 indicates that no data sheets are required for this
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test; but the body of the procedure requires data to be recorded and a data sheet is contained in the procedure.
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Licensee Response:
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Section 2.3 is in error and will be corrected before the procedure is used.
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Coment 2:
Prerequisite tests listed in Section 5.1 and required to be com--
pleted before this test is started have not been provided with sign-of f spaces.
Licensee Response:
- This is an oversight and will' be corrected.
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RO Rpt. No. 50-302/74-6-5-
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Comment 3:
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Section 9.2.1.B requires specified data to be recorded, but does specify where it is to be recorded and no data sheet has been
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provided for recording the data.
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Licensee Response:
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t The appropriate data sheet will be added and th' wording of
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e Section 9.2.1.B will be revised to specify the number of the data sheet to be used.
Comment 4:
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Sign-off requirements for procedure steps do not appear to be consistent throughout the body of the procedure.
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Licensee Response:
This item has already been discussed by members of power testing.
Sign-off will be made consistent throughout this and other test O
procedures.
7.
Steam Generator and Pressurizer Safety Valves
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This item was initially discussed in RO Report No. 50-302/73-12, Details II, paragraph 2.d.
Discussion during this inspection with licensee representatives in the power testing group indicated that the licensee was undecided as to whether the valves would be tested in place (installed) bench tested and then installed.
At the :nanage-ment interview, a licensee representative stated that FPC had made the decision to bench test the valves. He stated that the valves
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would be bench tested per approved test procedures in accordance with the FPC test schedule, and asked if the Comnission had any concerns regarding bench testing of safety valves.
The inspector replied that he would request Region II management guidance and would inform the licensee by phone of any problem that might exist.
On April 2, 1974, the inspector advised a licensee management representative by phone that bench testing was considered to be an acceptable method of testing the safety valves. This item is considered closed.
8.
Test Data The inspector discussed the method of recording and changing test data with. licensee representatives.
He explained that he had not seen a
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RO Rpt. No. 50-302/74-6-6-
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any. instructions addressing this topic in any of the test program documents.
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A licensee representative stated that appropriate instructions would be iscued to assure that data was recorded legibly and in ink, and that when it was necessary to change data, it would be lined out, corrected, initialled, and dated.
At the management interview, a
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licensee representative stated that some of the above instructions
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had been added to the TPG.
It was further stated by licensee
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representatives at this time that appropriate and complete instructions would be provided, and that if those in the TPG were incomplete, they would be supplemented. The inspector has no further questions cea-
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cerning this item.
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9.
Test Procedure Changes
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The TPG allows minor changes to be made to test procedures by the test supervisor without any change from control. The test super-visor can line out the part being changed, make the correction, and
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initial it,in the procedure and is not required to fill out a change sheet or addendum. The inspector stated that some formal change control should be initiated for all changes to test procedures.
A licensee representative stated that this subject would be dis-cussed with FPC management and resolved prior to the next inspection.
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10. PWR Main Steam Line Isolation Valves
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The information requested on this subject by Regulatory Operations letter,. RO:II:NCM, 50-302, dated February 20, 1974, was transmitted to Region II and Headquarters by FPC letters dated March 18, 1974, and April 14, 1974. The data provided will be evaluated by Headquarters personnel. No further inspection effort is planned for this item.
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Ltr to Florida Power Corporation fm N.
C. Moseley
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dtd APR 3 01974
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DISTRIBUTION:
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H.
D. Thornburg, RO
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C-10:HQ (4)
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Directorate of Licensing (4)
DR Central Files
- PDR
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- Local PDR
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- NSIC i
- DTIE, OR
- State
- To be dispatched at a later date
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