IR 05000312/1974005
| ML19309A239 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 07/08/1974 |
| From: | Garvin L, Andrea Johnson, Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19309A230 | List: |
| References | |
| 50-312-74-05, 50-312-74-5, NUDOCS 8003260938 | |
| Download: ML19309A239 (8) | |
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DIEECTOT.m CF RECULATORY OPERATIO35
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30 Inspection Report No.
50-312/74 :05
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- 1,1censee: Sacfamento"tanicipal Utility Distr,1ct Docket No.
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Saddamento, California
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License No.(s) CPPR-
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Priority Tacility: __ Rancho Seco
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Category _
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Imcation: Clay Station, California
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Type of Facility:
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Type of' Inspection:
Routine. Announced
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Dates of, Inspection:
June 10-1.3 and 24-25,'1974
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Dates of Previous Inspection: April 16-18, 30 and May 6, 7 and 9, 1974
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Principal Inspector: [/
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A. D.
nso'n,. Reactor Inspector
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Accompanying Inspectors:
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L. J. G rvi Reactor" Inspector
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I T. Young Jr., Reactof Inspector
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j, Other Accompanyitig Personnel:
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L..L.
Beratan, Senior Structural l'
Engineer, HQ
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Reviewed by:.,
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6. S Speneed, Chief, Reacto,r' Construction (Date)
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and Operations Branch
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8003260 938
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SUMMARY OF FINDINGS
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Enforcement Action
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None
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Licensee Action on Previously Identified Enforcement Items
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None
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Unusual occurrences The circunstances associated with the' malfunction of the stop-check valves in the decay heat system and damage,to a Class I seismic support on the feedwater line were examined. The corrective measures described
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in the licensee's two separate reports of these items to the Directorate
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of R,egulatory Operations, both dated June 19, 1974, were confirmed during the inspection.
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Design Changes The seismic evaluation of the as-built piping in the spray ponds disclosed that the eight (8) 20-inch diameter vertical risers from the main coolant lines require modification to preclude excessive stresses during the postulated seismic event.
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Other Significant Items
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Based on the results of the vibration testing program conducted on the "C" reactor coolant pump, the pump will be balanced for four-pump operation at hot conditions and a selective pump operation sequence will be employed to provide "last on-first off" operation of the "C" pump.
(Paragraph 5 of Details)
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The interim summary report.of the test programs to measure piping strains, deflections and expansions during hot functional testing
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indicated that the piping was generally found to be properly supported and operated as designed. Exceptions were documented and corrective
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measures taken.
(Paragraph 4 of Details)
C.
The plant instrument calibration and test procedure program was found to be consistent with the guid.ance provided in ANSI 18.7.
(Paragraph 7,of Details)
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Procedures to be used during precritical and power ascension test were fo,und to be consistent with the guidance provided in the
" orange" book / Regulatory Guide 1.68.
(Paragraph 6 of Details)
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Completion of the corrective actions indicated in the significant E.
deficiency reports submitted by the licensee to the Directorate of Regulatory' Operations on April 24 and May 10, 1974 were confirmed.
These reports concerned the response time of the reactor coolant pressure t'ansmitters and the makeup pump recirculation orifices.
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A new tend'on has been installed in H-50 of the containment building.
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A tendon t'est program demonstrated that repeated lift-off testing of a tendon can be conducted without adverse effects.
(Paragraph 8
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and Section II of Details)
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I The inspections of Class I bolts requested by RO Bulletins 74-3 and G.
3A have be'en completed. The results were being evaluated by the contractor. Reportedly, no defects were identified.
Management Interview
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The inspectors met with the following personnel on June 25, 1974 to
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discuss the scope and findings of the inspection:
SMUD'
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D. Raasch, Manager, Generation Engineering, R. Rodriquez, Manager, Nuclear Operations
J. Hiltz, Resident Engineer J. McColligan, Asst. Supt. Technical Support L. Schwieger QA Director
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J. Jewett, QA Engineer J. Sullivan, QA Engineer
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W. Stinchfield, Project Manager W. Miller, Project Field Engineer
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The licensee made the following commitment:
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The circumstances associated with the apparent design deficiency in the spray pond piping will be reported in writing to the AEC pur'suant to 10 CFR 50.55(e).
(Design Change Section, above)
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REPORT DETAILS - SECTION I
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Persons Contacted
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R. Rodriguez, Manager, Nuclear Operations.
P. Dubre', Assistant Plant Superintendent, Operations J. McColligan, Assistant Superintendent, Technical Support R. Colombo, Technical Assistant D, Whitney, Plant Nuclear Engineer
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G. Coward, Plant Mechanical Engineer
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L. Schwieger, QA Director
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J. Jewett, QA Engineer J. Sullivan, QA Engineer J. Haratyk, Electrical Engineer L. Kielman, Project Mechanical Engineer
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P. Dean, Instrument and Control Foreman
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Bechte'l
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W. Miller, Project Field Engineer L. Blackburn, QA Clerk A. Stenersen, Project QA Engineer R. Andersen, QA Engineer 2.
. Status of Construction and Preoperational Test Program
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Although there are still some secondary plant construction items to be completed prior to power operation of. the plant, the nuclear systems have been completed. Upon satisfactory completion of the safety features actuation system test, the necessary pre-fuel load testing program will have been* completed. The schedule for performing the test has been delayed due to a carpenter union strike. Union clearances have been obtained to permit some necessary work to be completed on June 29 and 30. Therefore, the test was expected to begin on July 1, 1974. Assuming a successful test, the facility could be ready for fuel loading by July 12, 1974.
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The master construction completion list and the file of uncompleted
nonconforming reports were examined to ascertain what significant safety related items had not been completed. The.following were considered to be the more significant items.
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a.
Re-installation of Class I snubbers removed for inspection and rework as necessary to preclude premature failures.
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Seismic evaluation of as-built hangers for restraint of Class I piping systems.
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Local leakage ratc testing of ten containment penetrations.
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Functional testing of reactor building purge systems.
Modification of the vertical risers from the main lines supplying e.
coolant to the headers for the spray ponds to reduce stress levels during a seismic event.
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Installation of required supports on cables leading to several electrical penetrations.
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Licensee Action on Previous Commitments a.
A draft administrative procedure controlling work requests was examined. The procedure was found to contain provisions to.
assure appropriate inspection and/or testing after maintenance
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activity on safety related systems.
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The procedure and/or schedule to assure periodic review of
. operating procedures had not been formulated.
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An instruction had been issued by the Plant Superintendent directing that the data obtained from those preoperational tests that have been partially performed, but cannot be completed until after fuel loading, be reviewed and approved prior to
fuel loading.
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4.
Class I Piping Restraint and Expansion Test Results The interim te t report of the program carried out to measure piping strains, deflections, expansion and vibraticas during the hot functional test (HFT) was examined. The tests were conducted in accordance with the requirements of paragraph 1-701.5.4 in the ASME I!uclear power piping code B31.7 and Appendix 4A of the FSAR.
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The Summary of the report stated that, "in general, the measured
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static and dynamic strains were lower than predicted and in all
cases met the ace tance criteria."- The measured deflections fell within the predictitd ranges in all except four cas.es.
The piping
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was generally found tc be properly supported and operated as designed.
The report concluded that, "the stress and deflections due to vibration and thermal growth for the piping systems operated during i
HFI are acceptable." The inspector confirmed r. hat the exception
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i areas were documented and appropriate corrective measures taken.
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5.
_ Reactor Coolant Pump-
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A test program was performed af ter hot functional testing (HFT) to determine the cause' of an unusual vibration characteristic exhibited by the "C" reactor coolant pump during HFT. The licensee stated
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vibration was hydraulic unbalance. The pump will be balanced at the shaf t coupling to achieve an acceptable run-out and frame
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vibration condition. The balancing was to be optimized with four pump operation at hot conditions. This effort is being made to obtain a more favorable pump lifetime warranty benefit.
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Precritical and Power Ascension Testing Procedures t
The following procedures were examined'with respect to review
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requirements, acceptance criteria, precautions, initial conditions and test conditions:
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TP 800-28 Pseudo CR Ejection Test
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TP 800-11 Core Power Distribution
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TP 301-03 Nuclear Instruments Preoperations Calibration
'TP 600-12 Pressurizer Operations and Flow Test TP 800-42 Unit Loss of Load Test TP 710-2 Post Fuel Load CRD Trip Test TP 800-26 Loss of Offsite Power Test i
TP 710-1 Zero Power Physics Test
,The stated requirements of the FSAR and Technical Specifications
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were found to have been met by the procedures.
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7.
Calibration and Test Procedures
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The instrument calibration and ' est procedures have' all been written t
and either approved or in the process of being reviewed for approval.
The calibration program has been established with a vendor contracted to calibrate the test standards and all in-plant instruments will be calibrated to the test standards by plant personnel. The program was found to be consistent with the requirements provided in ANSI 18.7.
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Containment Tendons
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Tendon H-50 has been replaced by new strands and renamed tendon H-50A. The new strand material connists of two heats of material that were tested to insure that they met ASTM A416 grade 270 re-quirements. Mill test reports and fabrication records for the wedge material showed that these materials met specification requirements.
Examination of construction records disclosed that the tendon strands had been installed, grease added and tensioned. No anomalies were noted in the examination of the construction records.
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O DETAILSECT50N II V
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RO Report No. 50-312/74-05 DETAILS:
Prepared by:
LcT/
4-2 /"hf
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L. L. Besatan Date
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Senior Structural Engi-r Technical Assistance th Directorate of Regu;
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- Date of Inspection: June 12-13, 1974 d * 2 Y-7 Y ~
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Reviewed by:
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Karl V. Seyfriy/[ Chief Date Technical Assistance Branch Directorate of Regulatory Operations
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Iersons Contacted:
F. E. Abdon, Bechtel, Snio
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H. R. Reuter, Bechtel Corporation p
A. J. Landler, Southern California Edison
G. Drew, Sacramento Municipal Utility District
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J. Hiltz, Sacramento Municipal Utility District J. Sullivan, Sacramento Municipal Utility District E. Davis, VSL Corporation
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R. Friedrich, VSL Corporation D. Swanson, VSL Corporation J. Garvin, Inspector, RO:V *
W. Albert, Inspector, RO:V *
Dr. C. P. Tan, Structural Engineering Branch, L
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Background:
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Because of the difficulties encountered in the lift off test
performed on tendon H50 in the Sacramento Municipal Utility l
Dis trict (SMUD) containment building. wall, SMUD committed to j!
have lift-off testing perfor=ed on a test tendon installed in a testbed. This testing was performed on June 12, 1974 at the
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fabricating plant of the VSL Corporatica, in Campbell, California.
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Tendon Test:
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A thirty-foot (30') ES-55 tendon was. stressed to 70 percent of
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k yield with a normal VSL stressing jack.
At one end the strands tl
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protruding from the anchor head were cut so that the protrusion
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into a VSL 900-ton lift-off Jack. The pulling wedges were seated j
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by tapping the wedges with' a 2 X . and hammer. The jack was
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pressurized-to 6900 psi which. caused the jack to apply a force on the tendon equal to 10, percent of its yield strength.
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Paint was { applied to the wedges in the washer contacting the
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bearing place to serve as an indicator if there was any movement of the wedges during the lif t-off test. The tendon was gripped and; stressed to 70 percent of yield 15 times with the gripper in the jack being rescated each time. There was no indication of movement of the holding wedges.
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i It was observed that the 7!s inch protruding ends of the strands when gripped by the gripper wedges in the jack, came to within
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a % inch from the back of the wedges. The strands were fully gripped by the holding wedges and the shortness did not invali-date the t,est.
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At the conclusion of the tent, thieendsofthestrandswere examined for broken wires ar.d none were detected.
It was noted'that the jaws of the gripper wedge left significant
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indentations on the wires which make up the strands.
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