ML19248D642
| ML19248D642 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 06/19/1979 |
| From: | Carlson J, Faulkenberry B, Johnson P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19248D636 | List: |
| References | |
| 50-312-79-10-01, 50-312-79-10-1, NUDOCS 7908170123 | |
| Download: ML19248D642 (6) | |
See also: IR 05000312/1979010
Text
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U. S. NUCLEAR REGULATORY COMMISSION
OFFICE oF INSPECTION AND ENFORCEMENT
REGION V
Report No.
50-312/79-10
Docket No.
50-312
License No.
Safeguards Group
Licensee:
Sacramento Municioal Utility District
P. O. Box 15830
__ Sacramento, California 95813
Facility Name:
Rancho Seco
Inspection at:
Clav station, California
Inspection conducted:
May 7, 8,14,17, 22, 29-31, June 1, 2, 4-8 and 10-11,1979
Inspectors:
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Approved by:
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B. H. Faulkenberry, Cl ' f,-ReTctor Projects Section 2,
Date Signec
Reactor Operations
d Nuclear Support Branch
Sunmary: Inspection between May 7 and June 11, 1979 (Report No. 50-312/79-10)
Areas Inspected:
Inspection of plant operations, IE Bulletins, and operator
retraining pertaining to the "Three Mile Island" incident. The inspection
involved 160 inspector hours onsite by four NRC inspectors.
Results:
No items of nonconpliance or deviations were identified.
RV Form 719 (?)
7908170123
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DETAILS
1. Persons Contacted
- R. Rodriguez, llanager, fluclear Operations
- P. Oubre, Plant Superintendent
W. Ford, Operations Supervisor
- J. McColligan, Supervisor, Engineering and Quality Control
- R. Colombo, Technical Assistant
R. Wichert, Plant Mechanical Engineer
T. Tucker, Shift Supervisor
J. Mau, Training Supervisor
H. Heckert, Engineering Technician
R. Low, Electrical Engineer
f1. Young, Electrical Engineer
- J. Sullivan, Quality Assurance Engineer
The inspectors also interviewed several other licensee enployees,
including members of the engineering and reactor operations staffs.
- Denotes those attending exit interview.
2. Licensee Actions to IE Bulletin 78-05B
The inspector examined pertinent licensee documents including administrative
orders; standard operating, surveillance, alarm response and emergency pro-
cedures; test data; and minutes of the Plant Review Committee.
In addition,
the inspectors witnessed certain testing of related components and systems
addressed in the bulletin.
Based on the foregoing, the inspectors verified
the information provided in the licensee's response to the Director, IE:V,
dated !1ay 2,1972, as follows:
a.
Procedures related to the natural circulation mode of operation had
been developed, approved and inplemented,
b.
Licensed operating personnel had been instructed in the new procedures.
c.
The operations personnel were found'to understand the technique for
determining the degree of subcooling of the reactor coolant system.
d.
The natural circulation cooldown procedures caution operating personnel
to maintain pressurizer level between 150 + 50" while raising 0TSG
1evel s.
e.
The natural circulation cooldown procedures provide direction in the
event of loss of all feedwater flow while in the natural circulation
mode of operation.
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f.
The operating procedure and standing orders prescribe requirements to
assure that vessel pressure / temperature limitations are not violated
by operation of the high pressure injection pumps.
9
The reactor high pressure trip setpoint and the PORY initiation setpoint
were changed on April 22,1979 (see IE Report flo. 50-312/79-07).
h.
The licensee's casualty and alarm response procedures provide guidance
on anticipated instrument response and annunciation for each of the
transients listed in IE Bulletin 79-05B.
i.
Plant operators and supervisory personnel had been instructed in the
requirements, provisions and directives for early notification of
serious events.
j.
In response to IEB 79-05B, the licensee installed a speaker phone in
the control room. This has been connected to the flRC's dedicated
telephone line, and was tested on 6/14/79.
The licensee does not
plan to provide an additional man on each shift to communicate with
flRC in the event of an accident, but, rather intends to call in per-
sonnel as needed. The speaker phone will enable control room operators
to keep flRC informed until additional personnel arrive at the site.
k.
The licensee response to items 5 and 7 of IE Bulletin 79-05B were
submitted within the time period specified.
1.
Procedures examined during the inspection included the following:
A.46, Rev. 6 - Main Turbine System
A.51, Rev. 5 - Auxiliary Feed System
A.64, Rev. 5 - Generator and Exciter System
B.2, Rev. 11 - Plant Heatup and Startup
B.4, Rev. 9 - Plant Shutdown and Cooldown
D.1, Rev. 3 - Load Reject
D.2, Rev. 2 - Turbine Trip
D.3, Rev. 6 - Reactor Trip
D.5, Rev. 10 - Loss of Coolant /RCS Pressure
D.10, Rev. 4 - Loss of RCS Flow /RCP Trip
D.4, Rev. 2 - Loss of Makeup / Letdown
D.14, Rev. 5 - Loss of Steam Generator Level
H2YSA, Rev. 2 - Turbine and Secondary System Panel A
SP 210.01 A - Quarterly Turbine / Motor Driven Auxiliary Feed
Pump Surveillance Test
SP 210.01B - Quarterly Moter Driven Auxiliary Feed Pump
Surveillance Test
3. Comission Order 7590-01
The fluclear Regulatory Commission (fiRC) issued Order 7590-01 to the
Sacramento Municipal Utility District (licensee) on May 7,1979.
The
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Order directed that the Rancho Seco Nuclear Power Plant remain shutdown
until certain actions had been taken by the licensee. The licensee by
letter dated May 14, 1979, provided the Commission the status of the
actions required by the order.
Based on examination of the licensee's
procedures, pertinent records, observation of equipment tests and dis-
cussions with licensee representatives, the inspectors confirned the
following:
a.
Plant Procedure A.51, Auxiliary Feedwater System, has been changed
to provide instructions to the operators for operation of the Auxiliary
Feedwater System Independent of ICS controls.
In connection with this
procedure, the inspector witnessed a functional test of the
"A" SFAS
bypass valve to verify that the valve operator will sustain the addi-
tional starting current resulting from a number of short jogs.
The
"A" bypass valve (SFV-20577) operated properly for two complete cycles
and over 40 short jogs in close succession.
b.
A hard-wired reactor trip circuit that will actuate on loss of nain
feed water and/or turbine trip, has been installed as described in
the licensee letter dated May 14, 1979.
c.
Operating procedures prescribing action in the event of a snall break
have been developed and implemented. The analysis for potential small
breaks has been submitted to NRC by the flSS supplier, Babcock and
Wilcox Company.
d.
Licensed operators were being provided Three Mile Island training at
the Lynchburg simulator.
On May 14, 1979, a sufficient number (8) of
licensed operators had received the prescribed training to assure that
at least one Senior Licensed Operator with TMI-2 training will be
available and assigned to the Control Room as required by the Commis-
sion's Order,
e.
The timeliness and reliability of delivery from the Auxiliary Feedwater
System has been upgraded by the actions identified in Enclosure 1 of
the licensee's letter of April 27, 1979, as reported in thc 'icensee's
letter to the Director, Office of Nuclear Reactor Regulation, dated
May 14, 1979.
The inspectors verified that auxiliary feedwater flow
rate indicators (reading in GPM) had been installed in the control
room and functionally tested. An additional alarm at the 3-foot
level in the condensate storage tank was also installed by the licensee
(as requested by NRR).
f.
In addition to the procedures listed in the proceeding paragraph,
the inspectors examined the following procedures:
STP-827 - Test Reactor Trip From Generator / Turbine Trips
and/or loss of Main Feedwater
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STP-611 - Auxiliary Feedwater Control Valve Failure flode Test
SP 214.03, Rev. 10 - Locked Valve List
STP-612 - Auxiliary Feedwater Flow Indicator Functional Test
STP-070 - Auxiliary Feedwater Flow Verification Test
tio items of noncompliance were identified. However, the inspectors observed
that the reactor trips frcm the generator / turbine and loss of main feed-
water utilize a non-fail-safe design; i.e., the trip relays are required to
energize to initiate a reactor trip.
This condition was described in the
licensee's letter to the Commission dated May 14, 1979, and had been accepted
by fiRR TMI-2 task force personnel.
4. Operator Retraining
In company with an operator licensing examiner from fiRR, the inspectors
verified that the licensee had completed operator training activities as
prescribed by Comission Order flo. 7590-01, dated May 7, 1979.
This deter-
mination was based upon an examination of pertinent training records and
interviews with a representative number of licensed operators.
However,
additional training was deemed advisable and had been scheduled by the
licensee for completion during the week of June 11, 1979. The effectiveness
of the additional training will be determined prior to the resunption of
power operation.
The inspectors established the following from an examination of the training
records.
a.
Twenty-two indiv duals hold a valid f4RC license to operate the
i
Rancho Seco nuclear power plant.
b.
Fourteen of the licensed personnel had received TMI-2 simulator
training at Lynchburg, Virginia. The remaining eight operators
were scheduled to complete this required training by June 23, 1979.
c.
Licensed operators and Senior Licensed operators that had completed
TMI-2 training at Lynchburg were assigned to each shift consistent
with the Commission's Order and licensee commitments.
d.
All licensed operators had completed the special post-TMI-2
training program conducted by the licensee.
fio deviations or items of noncompliance were identified.
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5. Exit Interview
The inspectors n'et with licensee representatives (denoted in Paragraph 1)
on June 11, 1979, to discuss the scope and findings of the inspection.
The licensee indicated that all changes to procedures had been submitted
to IE for approval and that the additional training of operators requested
by flRR would corrence on June 11 and be completed by June 13, 1979. The
inspectors informed the licensee that no deviations or items of noncom-
pliance were identified during the inspection.
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