IR 05000312/1974007
| ML19309A422 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 09/27/1974 |
| From: | Book H, Andrea Johnson, Spencer G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19309A413 | List: |
| References | |
| 50-312-74-07, 50-312-74-7, NUDOCS 8003270865 | |
| Download: ML19309A422 (12) | |
Text
_
.
.
.
,
&
'
.
[
U. S. ATOMIC ENERGY COMMISSION (
DIRECTCRATE OF REGULATORY OPERATIONS
~
REGION V
'
'
.
RO Inspection 1eport No.
50-312/74-07 Docket No.
50-312 Licensee Sacramento Municipal Utility District Li -nse No. DPR-54
,
6201 S. Street, Box 15830 Priority
.
Sacramento, California Category B
Facility Rancho Seco Location Clay Station, California
.,
Type of Facility PWR, B&W, 913 MWe (2772 MWc)
Type of Inspection Routine, Announced & Unannounced
-.
August 14, 19, 20 and Dates of Inspection September 3-5 and 11-13,1974 Dates of Previous Inspection June 10-11 & 24-25, 1974
-
er/47 /7 Y
~
Principal Inspector M2bncA u
p.A.D.Johgson,ReactorInspector
.
Date Accompanying Inspectors )
i 9-77-7#
v L.J.parvin,ReactorInspector Date Y Wu G, J
'l~ Q 7 - 7'l M. H. Malmros, Reactor Inspector Date Wif$b/l 9-29-,Y R. F. Fish, Radiation Specialist Date
,
Other Accompanying Personnel: None 7/27/ 7b Reviewed by:
'k-0.DVtCt'l
G. S. Spencerd Chief, Reactor Constructica Date Operations Branch
$~ E N' lf
%
a i
H.' E. Hook, Chief, Radio 1cgical and Date i
Envirocnental Protection Branch s
80032706Y$~
,
.
- -
.
.
-_
_. -.,.
. -......
...
.. -.
..
,
.. _. _ _
,-I
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -
_ _ _ _ _ _ _ _ _ _ _ _ _
-
~
.'
.
.
l SUMMARY OF FINDINGS Enforcement Action
".
.
None
.
Licensee Action on Previous 1v Identified Enforcement Items Bone
.
Unusual Occurrences
.
'
The licensee's reports of the events and circumstances associated with
-
the following unusual occurrences were confirmed by examination of relevant records and thorough discussions with licensee representatives.
A.
Abnormal Occurrence 74-1, Failure of "B" diesel generator to start and attain proper voltage; reported to Directorate of Licensing by letter dated September 6, 1974.
B.
Abnormal Occurrences 74-2, Failure of isolation valve to open upon demand; reported to Directorate of Licensing by letter dated September 13, 1974.
C.
Abnormal occurrence 74-3, Reactor coolant system overpressure during heacup; reported to Director of Licensing by letter dated O
September 20, 1974.
.
~
Other Significant Items A.
Corrective measures related to significant deficiencies previously reported were confirmed to have been implemented as indicated in the reports from the licensee.
(Paragraph 3.of Details)
B.
The licensee had taken appropriate action on the previous commitments
-
related to (1) the administrative procedure for control of routine procedure evaluation and (2) the reporting of the identified de-ficiency found in the design of the spray pond piping system.
(Paragraph 2 of Details)
'
C.
The items identified in RO Report No. 50-312/74-06, Paragraph 2 of Details, were verified to have been completed as required prior to the initial loading of fuel into the reactor vessel. The facility Operating License DPR-54 was issued by the Directorate of Licensing on August 16, 1974.
(Paragraph 4 of Details)
%
'
.
.
.a v-s I
- - _.
e
.
,.
.
(
f-2-v D.
Initial fuel loading co==enced on Augue.t 19 and was completed on August 23, 1974.
(Paragraph 5 of De*. ails)
.
E.
Test results showed that the =1r'm m efficiencies for the charcoal and high efficiency part:.culate air filters were 99.58 and 99.90%
-
respectively.
(Paragraph 6.h of Details)
7.
The licensee programs related.to radiological protection training,-
personnel exposure monitoring, radiation detection instru=entation, respiratory protection equipment, preoperational tests of radio-active wasta systems, and emergency provisions had been implemented.
(Paragraph 6.a-g of Details)
Management Interview The inspectors met with the following licensee representatives on September 13, 1974 to discuss the scope and findings of the inspection.
J. Mattimoe, Assistant Generni Manager, Chief Engineer D. Raasch, Manager, Generation Engineering
)
R. Rodriguez, Manager, Nuclear Operations L. Schwieger, QA Director
!
1. Miller, Chemical & Radiation Protection Supervisor J. Jewett, QA Engineer l
J. Sullivan, CA Engineer-Js Lee, Senior Chemical Engineer
-
In view of the consequences encountered after the loss of the "D" inverter on September 11, 1974 and considering the i=portance of pressurizer level indication to the operating personnel for safe operation of the plant, the' licensee representatives stated that a change to the technical specifications would be requested. The change will specify requirements for pressurizer level instrumentation during plant operation.
- The manual switch installed to provide alternate power to the a.c.
control power from the "D" inverter will be replaced with an automatic switch.
(See licensee's Abnormal Occurrence Report to the Directorate of Licensing dated September 20, 1974 for details.)
,
.
'
\\
-
O(J
-
,
-
..
.-
-
-
-
_
,
.
.
N REPORT DETAILS 1.
Persons Contacted'
Sacramento Municinal Utility District
'
-R. Rodriguez, Manager, Nuclear Operations P. Oubre' Assistant Plant Superintendent, Operations
- J. McColligan, Assistant Superintendent, Technical Support R. Colombo, Technical Assistant D. Whitney, Plant Nuclear Engineer G. Coward, Plant Mechanical Engineer 3. Spencer, Shift Supervisor R.. Dietrich, Nuclear Engineer L. Stevenson, Supervising Instrument and' Control Engineer L. Schwieger, QA Director J. Jewett,-QA Engineer
,
J. Sullivan, QA Engineer R. Miller, Chemical and Radiation Protection Supervisor D. Martin, Plant Health Physicist.
D. Abbott, Associate Engineer D. Krisha, Test Coordinator. (Bechtel)
F. Kellie, Senior Chemical and Radiacion Protection Assistant Bechtel L. 31sekhurn, QA Clerk y
-
Herald Fire Department
-
L. Bales, Chief 2.
Licen'see Action on Previous Commit =ents a.
An administrative procedure has been established to control
,
the periodic review of Nuclear Generation procedures. The l
procedure (AP-27) provided for a method of up-dating procedures and a record to verify the procedure reviews.
l b.
The significant design deficiency related to the spray pond
,
piping was reported to the Directorate of Regulatory Operations by letter dated July 11, 1974 pursuant to the requirements of 10 CFR 50.55(e).
3.
Significant Deficiencies - Correctite Actions The inspectors confirmed from documentation at the site, by obser-
.,
'
vations, and through discussions with licensee representatives that i
corrective action had been completed on previously reported items j
as indicated for each below.
!
e
.
,.,
,--
-,
,. -
- -, - - -,, -
-,
., <.
-~.
,,--.-~,.-..w
--
w
-
--,e-
- - - -,
e--w e --
.
.
.
,
,
.
a.
High Pressure Injection System (Licensee 1tr dtd 8/1/74)
A motor operated valve has been installed between the makeup tank and the high pressure injection pump header. The valve'
,
had been satisfactorily tested to demonstrate that it will automatically close upon actuation of the safety features s7ates.
'
b.
Internals Handling Fixture (Licensee 1tr dtd 8/21/74)
To preclude malfunction, the internals handling fixture has been modified by attaching a plate to the bottom of the threaded rod. This will prevent the spherical nut from unthreading as
~
reported in the licensee's letter.
i
'
c.
Reactor Coolant Flow Miscalibration (Licensee 1tr dtd 8/23/74)
The calibration procedures for the reactor coolant flow in-strumentation and the reactor protective system power / imbalance / flow channel have been changed so that the actual, rather than design, flow rate at 100% power is used to determine the
,
appropriate settings of the protective systems trips.
d.
Spray Pond Piping (Licensee 1tr dtd 7/11/74 and Licensee 1tr to Licensing dtd 7/26/74)
,
Installation of the expansion joints in the spray pond risers
'
to decouple seismic loads transmitted between riser pipes and distribution headers were examined. The =odifications were.
.found to have been completed as described in the licensee's letter to Licensing. Material certifications and NDE results were included in the inspector's a - 4n= tion.
,
s.
CRDC's AC Breaker Cabinet (Licensee 1tr dtd 8/21/74)
The inspectors verified that attachment of the AC breaker cabinet to the floor had been redesigned and fillet welds added between the cabinet and the floor mounting to assure an
,
i installation able to withstand the design seismic criteria.
,
A.
Issuance of Oceratinz License On August 14, 1974, the inspectors confir:cd that the licensee had taken appropriate action to cc plate the ite=s identified in 10 Report No. 50-312/74-05, Details, Paragraph 2.
In addition, the inspectors verified from the records that the preoperational tests
vl
.
.
.
-
.
-.._
._
-
.-
--
_
_
-
.
,
'
'
.
.
.
.
.
5-
-
to be completed prior to fuel loading had been satisfactorily performed.. Prior to fuel loading on August 19, 1974, the inspectors c.ompleted the verification that all preoperational test results of
-
.
safety related syste=s had been evaluated for technical adequacy by l
the Test Working Group. Nonconforming items identified during
,
i tests were found to have been handled in accordance with the re-quirements of the licensee's-QA program.
On August 16, 1974 the Directorate of Licensing issued the facility operating license, DPR-54.
5.
Initial Fuel Loading The initial fuel loading commenced on August 19, 1974 with the first fuel assembly placed in the core at 11:47 p.m.
Tlie loading
'
of the 177 assemblies was completed at 1:42 n.m. on August 23, 1974. The preparation and performance of the initial fuel loading by the SMUD personnel were witnessed on August 19 and 20.
The following observations were made by the inspectors:
a.
Communications
-
Consnunications for the control of the fuel loading operation were established at designated locations in the Reactor Building, Fuel Building and the Control Room. The phones were manned continucusly during all fuci : vc=cn hy assigned persc n:1 ::.
c-the designated locations. SMUD instructions required that fuel movement cease if commmications were lost at any of the
~
designated locations. The review of the final documentation confirmed that fuel loading stopped when one of the two phone lines failed. Following repair of that circuit, fueling continued.
b.
Crew Requirements
The crew assignments for the initial fuel loading were established by published instructions with specific individuals assigned as Shif t Supervisor, Control Room Operator, Reactor Building Senior Licensed Operator, Fuel Handling Equipment Operator,
,%
Shif t Test Engineer, Data Takers, I/M Plotter, Plant Operators and Helpers. Three Senior Licensed Operators were assigned to each shif t as Shife Supervisor. Control Rocs Operator and
.
Reactor Buildine Senior Licensed Operater. The
'a'-"-
crav requirenants est:blish:d by the' Technical Specifications for fuel loading were verified to h:ve been =2t at all tinas. Th2 fuel loading was performed on a twenty-four hour basis, con-
. sisting of three-eight-hour shif ts.
Eac.;. shif t crew was assigned nine hours on-shift-tf=e with the first '
ured for crew briefing and shif t turnover.
,
S
,
e
.
...
..
p
.,
-,
.
-
,
,.
._
.
-
.
-
.
.
.
.
,
'
,
6-
-
~
c.
Procedures
.
The initial fuel loa' ding procedure, STP 200/Rev. 5, was available and used by personnel in the Reactor Building, Fuel Building and Control Rocm. The master' copy of STP 200/5 was
.
maintained by the Shift Test Engineer.
The check lists and signature signoffs contained within STP 200/5 were reviewed and verified to accurately rei' lect the i
current status of the fuel loading and plant conditions and were consistent with the requirements of both the procedure and the Technical Specifications. Two changes were made to STP 200/5 during the course of the inspection and these
changes were verified to have been made in accordance with the station administrative procedure for reviewing and approving procedure changes.
The Master copy of the procedure was avamined following its review and acceptance by the Plant Review Committee and the Plant Superintendent. The Master copy contained the changes to the procedure with approval signatures. No anomalies were noted during the a - 4n= tion.
d.
Fuel Loading Performance Personnel operating the fuel handling equipment were under the
,,
direct supervision of the Reactor Building Senior Licensed
,
Operator. Specific assignments of personnel for the operation of fuel handling equipment were based on the individuals experience and training. The operation of fuel handling equipment in accordance with applicable SMUD operating pro-cedures was verified by observation of assigned operators during several fuel loading evolutions. The performance of
,
independent verification of fuel assembly identification, fuel assembly insert identification, and core positions as required by the initial fuel loading procedure, was confirmed by
'
observation at the applicable fuel loading increments.
N e.
Nuclear Instrumentation
'
e The nuclear instrumentation for monitoring the reactor. core during the initial fuel loading ce= prised the installed cut-of-core source ran;e datactors (::1-1 and ::I-2)' and
.co port:Ma auxiliary neutron detectors placed in the reactor vessel at designated core positions.
Tha calibration records for ;;I-l and NI-2 were reviewed and no discrepancies were noted. The
-
,
\\
.
,
a i
.
+.
-+
,.*s-aw-e,y
~m w
+'w-
-
,
.,
'
-
-
s
--
,
calibration records for'the Babcock & Wilcox supplied auxiliary detectors were not readily available. A sour'ce range plateau calibration of the auxiliary detectors was performed by S!G
'
personnel prior to the start of fuel loading.
It was verified that a count rats of two counts per second or greater was
,
indicated on the source range instrumentation when the source assemblies were loaded.
(Actual counts varied from 221 to 1050 counts per second.).A minimum of two channels were
operable during fuel movements resulting in a change in core geometry and at least one channel was required to be operable for continuous monitoring of suberitical multiplication of the
core at all other times. As a result of leakage past the seal of the out of core instrument areas, the cables to NI-l and 2 were out of service during part of the fuel loading period.
An auxiliary out of core chamber was temporarily installed..
Prior to completing the core loading, the cables to N1-1 and 2 were replaced with the subsequent return to service of the out-of-core instruments. The licensee indicated the seal for i
the covers of the instrument areas will be = - 4ned and necessary corrective action will be taken to preclude leakage i
during the next refueling period.
f.
Inverse Multiplication Plots An inverse multiplication plot (I/M Plot) was maintained for each source range 2.ndication channel.
Ihe I/H plots were
'
.. _
-
saintained separately in the Control Room and the Reactor Building. Observation of plotting techniques and data correlation were confirmed to be in compliance with the requirements of the initial fuel loading procedure. Source range count stabilization and correlation with the I/M plots was required t
prior to the disengagement of the fuel handling device from each fuel assembly loaded. Plots of the recent loading of the
.
Three Mile Island plant were available for comparison and were observed to be consistent with the Rancho Seco loading. Final data and the plots of I/M were reviewed. No anomalies were noted.
g.
Boron Concentration
,
The mini== baron concentration of 1800 ppm in the reactor coolant was verified to have been maintained at all ti=es
'
during the fuel loading. A review of the che=istry racerds confirmed that the sa=pling frequency and beren ccacentration.
measurement met all require =ents.
The reactor was sa: pled at
.
.
-
--
- -
.
-
e.,
, _
_
.-,..w-,.
a y
.
-
-
~,
,,w,.
-
.
..
.
,
.
,
-
,
-8-four hour intervals and daily samples were obtained from support systems containing borated water. The reactor coolant had been routinely sampled for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to installation of the first fuel assembly.
.
h.
Access Control
=
Personnel access to the fuel loading areas in the Reactor Building and the Fuel Building was controlled by the pro-cedural requirements of the. fuel loading procedure and the radiological work permit issued for initial fuel loading.
During a tour of the buildings involved the inspectors ver-ified that 1) access was limited to guarded entrances, 2) access lists of authorized personnel were maintained, 3) appropriate clothing requirements were posted, 4) check lists of personnel in the controlled areas were maintained and 5) personnel radiation exposure monitoring was required.
6.
Radiological and Environmental Protection
\\
a.
Training
..
i The licensee has established a radiation safety training program that must be satisfactorily completed by persons who will be entering controlled areas unescorted. Satisfactory completion of the course means passing the written examination with a grade of 70% or better. A mir'mn= of three and one
-
i half hours of instruction is used to cover the following topics: emergency plan, basic radiation theory, AEC and Bancho Seco dose limits, biological effects of radiation, i
dosimetry equipment, internal exposure, dose control =ethods and dose record system, control zones, contamination areas and control of conenmination, radiation monitors and inplant
,
monitors and the radiation work permit sysi:em. According to
- '
the licensee, about 250 persons have taken the course to date.
The records consist of the names of the attendees and whether.
they passed or failed.
'
i i
,
b.
,
,
The emergency plan includes a listing of emergency supplies to be kept at the two assembly points and medical supplies available at the site. The inspection confir=ed the required items were in the First Aid Rec: and in kits located within the plant. With one exception, the supplies in tha ene assenbly point cabinet inspected included the items required
.
.
e
%d
$
t J
.
.
._ _
-..
_.._
.. r '
,
... _..
i
.
~,
..,.
..-
-
,
-
,
. - - - -
. _.
. _ _ _
.
-
,
P
.
.
_9_
by'the plan. 'There was no portable walkie talkie at the assembly point. The licensee explained that the limited number of walkie talkies on site were all required to load the fuel in the reactor. Prior to the mant.gement meeting on September 13, 1974 the walkie r=1kies had been returned t.o the
-
assembly point cabinets.
The emergency plan identifies the Herald Fire Diatrict as the local fire support organization.- The inspection disclosed that the District has 29 volunteers and 9 trucks. According
,
to Chief Bales, the Rancho Seco site is within their fire district. There have been no written agreements between SMUD and the District. According to Chief Bales,.SMUD would furnish any special protective clothing required when fighting a fire at Rancho Seco and perform necessary surveys. Chief Bales also confirmed the information contained in Paragraph 9 of
,
Report No. 50-312/74-04.
c.
Portable and Laboratory Instrumentation The licensee has received and put into operation the portable survey instrumentation. This instrumentation includes the following:
6 Cutie Pie type meters, 7 GM type meters, 3 ion chamber type meters, 1 alpha gas proportional meter and 2 neutron survey meters. The licensee has also received S laboratory type monitors, a hand and foot counter, a personnel
-
monitor, a tritium air monitor and 2 portable air monitors.
The licensee has 4 air samples, two have gasoline engines. -
The laboratory instru=entation was found to be as described in Section 11.4.6 of the FSAR.
In addition, the licensee has obtained a GeLi detector for use with the multichannel analyzer and a second gas flow porportional counter.with scaler.
- I d.
Protective Clothing i
The licensee has received protective clothing to be used by personnel working in contaminated or potentially contaminated areas. The protective clothing includes gloves (cloth and
,
neoprene), hoods and surgeon caps, shoe covers, coveralls and lab coats. The licensee said that supplies of these items
.
'
kept in the auxiliary building would be supported by addi-tional quantities in the storehouse. Autc=atic re-ordering levels have been established for the protective clotning ecpt
,
i in the storehouse. Ihe licensee has also purchased disposa'le o
coveralls and surgeon caps.
,
.
$
.
,
- - -
l.
_.
l
.
l
-
-
.,.
- -
,
.
,
- 10 -
.
a.
Respiratory Protection Program The. licenses has obtained respiratory protection equipment
.
from Mine Safety Appliances Company (MSA).. This equipment includes half-face and full-face masks for dust, fumes and
,
smoke, full face gas masks with various types of filters, and '
self contained breathing apparatus. The licensee also has an air supplied vinyl suit and full. face masks which use building supplied air. The licensee has prepared an audio-visual tape-which discusses and demonstrates the following respiratory portection topics:
the equipment and its operation, fitting the equipment, use of the equipment, removal of the equipment following use, maintenance and sanitizing the equipment..
According to the licensee, the' operations personnel will be
,
trained in the use of this equipment when the status of the
'
containmant building changes to a controlled area because of potential radioactive contaminscion.
f.
Personnel Exposures The licensee has purchased self-reading dosimeters to de-termine personnel exposure to neutrons. Three dosimeters will-be worn. One will determine the gamma exposure. A second will determine the fast neutron plus gamma exposure. The
,
third will indicate the thermal neutron exposure. The basic parsonnel axposure davice will ha the Tel. dyna Isotopas TfD
. _
,
badge for beta-gamma 0.xposure. Personal alarm dosimeters and j
chirpers are possessed by the licensee and TLD finger rings
'
will be used when necessary.
i g.
Preoperational Test Results
During this inspection the following test results were examined.
- No deficiencies were identified.
i
. (1) Boric Acid Concentrator System Functional Test (coolant i
radioactive waste system)
(2) Wasta Gas System Functional Test (3) Wasta Gas Sampling System Functional Test
,.
(4) Isotopic Calibration of Liquid Process Radiation Monitor h.
Ventilation and Filter Testing
,
'
The examination of the results of testing the charcoal and High Efficiency Particulate Air (EEPA) filters showed all filters met the acceptance criteria in the test procedure.
,
f
1,.
e
-
-
.
.
.
--
-.
.-
--
.
.
.
.
-
_.
__
'
c,.
.
- t
.
.
.
'
,
- 11 -
.
The charcoal efficiencies we're in the range 99.58-99.99%. The BEPA efficiencies were in the range 99.90-99.99%. One of the BEPA filters was in the exhaust system for th'e solid waste and
.
decontamination rooms. This exhaust system vezc.ed directly to
.
the atmosphere. The licensee has initiated a modification so that the exhaust air fres-these roces will go to the auxiliary
.
buil3ing exhaust sy, stem.
.
G
.
t
- - ens e
T e
.
I
.
O
,
I.
.
'
- -.