ML19281A427
| ML19281A427 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/24/1979 |
| From: | Donat T, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19281A421 | List: |
| References | |
| 50-327-79-02, 50-327-79-2, NUDOCS 7903130214 | |
| Download: ML19281A427 (5) | |
See also: IR 05000327/1979002
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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Report No.: 50-327/79-02
Docket No.: 50-327
License No.:
CPPR-72
Licensee: Tennessee Valley Authority
830 Power Building
Chattanooga, Tennessee 37401
Facility Name:
Sequoyah, Unit 1
Inspection at: Sequoyah Site, Daisy, Tennessee
Inspection conducted: January 3-5, 1979
Inspectors:
T. J. Donat
Approved by:
'/E Y
R. D. Martin, Chief
'Date
Nuclear Support Section No. 1
Reactor Operations and Nuclear Support Branch
Inspection Summary
Inspection on January 3-5, 1979 (Report No. 50-327/79-02)
Areas Inspected:
Routine, announced inspection consisting of witnessing
preoperational test TVA-13B(2) (Loss of Off-Site Power), review of appli-
cant response to previously identified items, and facility tour. The
inspection involved 28 inspector-hours on-site by one NRC inspector.
Results: Of the three areas inspected, no items of concompliance or
deviations were identified.
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RII Rpt. No. 50-327/79-02
I-1
DETAILS I
Prepared by:
7
T. J. Donat, Reactor Inspfctor
' Date
Nuclear Support Section No. 1
Reactor Operations and Nuclear
Support Branch
Inspection Dates: Ja ary 3-5, 1979
Reviewed by:
[W/77
R. D. Martin, Chief
Date
Nuclear Support Section No. 1
Reactor Operations and Nuclear
Support Branch
1.
Persons Contacted
Tennessee Valley Authority (TVA)
- W. F. Popp, Assistant Plant Superintendent
- W. E. Andrews, Plant Quality Assurance Staff Supervisor
- E. A. Condon, Preoperational Test Supervisor
W. Guinn, Operation Supervisor
R. H. Smith, Electrical Engineer
F. Siler, Instrument Engineer
P. Garrett, Nuclear Engineer
R. G. McCall, Mechanical Engineer (Engineering, Knoxville)
J. Lyons, II, Nuclear Engineer (Engineering, Knoxville)
- Denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findings
a.
In IE Report 50-327/78-04, Detail
I.5.b.2.b,
the inspector
identified that the maximum initial ice load weight used in
FSAR section 5.6.1 (Ice Condenser Refrigerator System Design
Basis) was inconsistant with the maximum values specified in
preoperational test W-12.1 (Ice Condenser Reactor Containment -
Rev. 0) step 5.3.1 and Special Maintenance Instruction SNP-
SMI-1-61-1 being used to load the Unit #1 Ice Condenser.
Ammendment 56 to the FSAR has revised the maximum Initial Ice
Load weight to 3.01 X 10s Ibm which is consistent with the
maximum weights used in W-12.1 and SNP-SMI-1-61-1.
This item
f
(78-04-04) is considered closed.
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RII Rpt. No. 50-327/79-02
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b.
In IE Report 50-327/78-17, Detail I.5 and 50-327/78-45, Detail
I.6.A,
discussed the commitments to monitor the Pressurizer
Relief piping downstream of the valves during the Hot Func-
tional Test Program.
On January 9,
1979, the applicant con-
tacted the inspector to discuss his program.
The applicant
stated that for safety reasons, a program of inspection prior
to and following the transients would be implemented.
He
stated that observers will be positioned on the containment
floor to observe as much pressurizer relief piping as possible
during the pressurizer blowdown and the procedure will be
modified to achieve this to a degree consistent with safety.
The inspector stated that a similar program of inspection of
piping, restraint, hangers, snubbers, and adjacent piping
prior to and subsequent to pressurizer relief lifting had been
found acceptable at other sites. The inspector stated that he
would review the final program as implemented in preoperational
test W-1.3 and would consider the item open until that time.
c.
In IE Reports 50-327/78-21, Detail
I.7,
and 50-327/78-35,
Detail I.8.b identified the need to verify the Diesel Gen-
erator's response in the event it is running and paralleled
with the normal power source when the site experiences a lo::s
of offsite power. The applicant has written a new preoperational
test procedure, TVA-13D Rev. 0 (Blackout with Diesel in Test
Mode), to verify the response.
The inspector has reviewed the
test procedure for conformance to the requiremer.ts of FSAR
Section 8.3.1.1 and Table 14.1, and Regulatory Guide 1.68.2,
1.41 and 1.108 and found no discrepancies. The inspector also
reviewed the calibration sheets for the diesel generator's
"51V Voltage Controlled Overcurrent Relays" to be utilized
during this test.
The preoperational test procedure TVA-13D
satisfies the concerns in open item (78-21-03).
This item is
considered closed.
3.
Unresolved Items
None
4.
Exit Interview
The inspector met with Mr. W. F. Popp concerning the inspection
on January 5,1979. The inspection lasted beyond the exit interview
,
and a call was placed to Mr. E. A. Condon on January 10, 1979, to
state that no additional findings were made af ter the exit interview.
The inspector summarized, as reported in the following paragraphs the
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RII Rpt. No. 50-327/79-02
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purpose and findings of the inspection. Within the areas inspected
no items of noncompliance or deviations were identified.
5.
Preoperational Test Witnessing
The inspector witnessed the performance of portions of preoper-
ational test procedures W-6.1A1 (SIS - Integrated Flow), and TVA-
13B(2) (Onsite AC Distribution - Loss of Offsite Power).
a.
The inspector witnessed the repetition of those portions of
W-6.1A1 necessary to obtain new data in place of the out-of-
specification RHR pump suction data discussed in IE report
50-327/78-45, detail
I.6.
It was noted that the appropriate
prerequisites had been re-signed, the chronological test log
was being used, and the official copy of the test procedure
was being used.
A review of the test data showed a disagreement, when all
pumps were secured, between the suction pressures recorded for
the RHR pumps and those for the containment spray pumps which
are located on the same elevation.
The applicant stated that
this was due to leakage past RHR pump discharge throttle
valves FCV-74-16 and FCV-74-23.
Subsequent closure of down-
stream valves FCV-63-93 and 63-94, securing gravity flow past
the discharge valves, resulted in RHR suction pressures which
were within specification and which agreed within measurement
accuracy with the containment spray pump suction pressures.
The inspector witnessed the performance of the portion of
paragraph 5.2 concerning the vibration of the RHR train when
in the recirculation mode.
Witnessed were the measurement of
vibration levels on RHR heat exchanger IB-B discharge piping
and the tracing of the piping associated with RHR train B while
monitoring it for excessive vibration.
The inspector did not
have any comments concerning the conduct of the test and
vibration measurement by the applicant.
b.
The inspector witnessed the performance of portions of TVA-
13B(2) - Onsite AC Distribution Test (Loss of Offsite Power). Prior to
and during the test the inspector reviewed the test prerequisite
section, section
2., to insure that all items had been signed by
the appropriate personnel. He performed an independent verification
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of the following prerequisites:
2.1.1.1 and 2.2.1.4 concerning Test
Record D.-awings being marked to show as built conditions and
acceptability of this by Engineering Design and Power Production,
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RII Rpt. No. 50-327/79-02
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2.1.1.2 concerning transfer of all necessary loads and electrical
boards to Power Production, 2.2.1.3 on most recent revision to
SOI 82.1 (Rev. 5) and SOI 57.4 (Rev. 4) being used; 2.2.1.7 on
differences in equipment configuration between preoperational
test TVA-13B(1) and this test, and 2.3.1.1 on Uncompleted Engineering
Change Notices to equipment operated during this test. No discrepancies
were noted during this review and verification.
The inspector witnessed the performance of the following tests
on diesel generator IA-A: Loss of Offsite Power (Non Accident);
Loss of Offsite Power followed by a Safety Injection; Simultaneous
Loss of Offsite Power and Safety Injection; Safety Injection
without Losing Offsite Power, and Simultaneous Safety Injection
and Loss of Offsite Power with ESF equipment aligned for full
flow conditions.
The inspector also monitored the performance
of Operations personnel in paralleling the shutdown boards
with the Offsite Power Bus and transfering the boards back to
their normal configuration in accordance with S01-82.1.
The
inspector had no comments on the conduct of the test.
6.
Plant Tour
The inspector toured portions of the turbine building, the control
bay and auxiliary instrument room, the auxiliary equipment building,
and the Unit No. I reactor containment.
Housekeeping and general
cleanliness were observed. No deficiencies were identified.