ML19260C535
| ML19260C535 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/28/1979 |
| From: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 1179, NUDOCS 8001070370 | |
| Download: ML19260C535 (9) | |
Text
.
h I
VanCO i
U VIRGINIA ELECTRIC AND POWER COMPANY December 28, 1979 I
l 1
Mr. James P. O'Reilly, Director Serial No.1179 Office of Inspection and Enforcement F0/WRC:11r 4
U.S. Nuclear Regulatory Comission Docket No. 50-338 i
Region II License No. NPF-4 l
101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 l
l
Dear Mr. O'Reilly:
j Per telephone request from L. Engle (00R) and E. We' ster (IE:RII),
i o
we have enclosed attachments concerning the status of refueling j
requirements.
The attachments represent identified commitments and does not include requirements (i.e., required equipment to meet LCO's, required sur-ve111ance, etc.) that must be met in order to comply with the Technical Specifications.
If questions arise concerning this information please call.
l i.
Very truly yours, c
W. R. Cartwright Station Manager WRC/11r Enclosures (3 copies) cc: Mr. Victor Stello, Director Office of Inspection and Enforcement i
\\
1696 077 I
8001070 3 ) b D
1
t{0RTH ANNA UNii 1 REFUELING OUTAGE REQUIREMENTS ITFM SOURCE STATUS REllARKS RCS Overpressure Protection NPF-4 License Amendment 3 DC-78-44 field work complete Before fill and vent.
~
Item 2.D(3)f and Technical Review complete System in use 12-24-79.
by SNSOC.
NRC has completed package for review (Kiddl.
Administrative Procedures, NPF-4 License Amendment 3 Fire Protection Program Controls and Fire Brigade Item 2.D(3)f Implemented 12-21-79 Program Containment Isolation Valves NPF-4 License Amendment 3 DC-78-70 Hardware complete.
Expect test completion Qualified Limit Switches Item 2.D(3)h and NRC One valve needs testing 12-29-79.
Inspection Item 78-14-02 prior to mode 4.
Degraded Bus Voltage NRC letter of 03-20-79 DC-78-69 field work complete Scheme and Technical Review complete by SNSOC.
NRC has completed package for review (Kidd).
Neutron Shielding LER/R0 78-33 and NRC DC-79-S07 field work complete Need to conduct radiatio 1 Inspection Item 78-14-04 and Technical Review complete surveys after startup.
by SNSOC. NRC review complete Pipe Caps on Spare Containment FSAR DC-79 ',10 field work complete Penetrations LER/R0 78-122 and NRC and Technical Review complete Inspection Item 79-09-01 by SNSOC. NRC review complete Control Room Bottled Air.
LER/R0 79-128 and NRC DC-79-S70 Hardware installed.
Expect test completion System Modification Inspection Item 79-39-03 Testing will be complete 12-30-79.
prior to Mode 4.
ARS Pipe Support Modifications LER/R0 79-151 DC-79-S72 as known field-See Vepco letter work complete.
Serial No.1152 Obtain Snubber Lockup and NRC Inspection Item 79-16-04 Complete cP Bleed Rate Data Data being reviewed by NRC (Kidd).
cr Inside Recirc Spray Motor LER/R0 79-43 and NRC Maintenance and testing <
O, Rearings Inspection Item 79-20-01 complete, NRC has completed m
their review.
v we
==========w-resee aamp.aum-gwe=oe w e-
_ e**= m me
NORTil ANNA UNIT 1 REFUELING OUTAGE REQUIREMENTS ITEM SOURCE STATUS REMARKS Replace Unqualified S0V's in IEB 79-01 DC-79-S50 field work complete Primary Sampling System LER/R0 79-65 and NRC and Technical Review complete Inspection Item 79-20-06 b SNSOC NRC h s c 1
pkckageforrevkewkbdhed j
SW Radiation Monitoring Pumps LER/R0 79-133 Pumps were repaired.
Test completion expected Tripped during Surveillance Need to be tested prior to 12-31-79.
Testing Mode 4.
i Seismic Qualification of Central LER/R0 79-149 See Vepco letter Serial and Safeguards Ventilation System ;
No. 1160.
Main Steam Pressure Transimitter LER/R0 79-142 Piping corrected. All ESF Tubing Swapped Sensors checked that send g g to SSPS.
Nonconservative Negative Rate LER/R0 79-152 Revised station curves.
Mode 2 item Trip Procedures will be revised i
on or about 01-02-80 Nonconservative Power Distribution Revised station cerves.
Mode 2 item and Rod Worths LER/R0 79-153 Procedures will be revised l
on or about 01-02-80.
I Nonconservative Calculations for LER/R0 79-143 I
Fq will be limited to 2.10 Mode 2 item and Fuel Clad Swelling per Technical Specifications. Tech Spec item (Pending OL Amendment for restart)
CDA and SI Reset LER/R0 79-141 See Attachment #1.
Repair 1-FW-111 (Leaking)
LER/R0 79-40 Valve checked - no problems found.
Reactor Trip Breaker P4 LER/R0 79-138 Testing will be completed Contacts (Testing) prior to Mode 2.
l 1696 079
s,
_fl0RTH ANilA UNIT 1 REFUELING OUTAGE REQUIREMENTS ITFM SOURCE STATUS REllARKS Repair Equipment that did not LER/R0 79-134 Equipment repairs being Testing completion Function during CDA Functional worked. Equipment will be expected 12-31-79.
Test
.gtjanallytestedpriorto Repair Equipment that did not LER/R0 79-132 Equipment repairs being Testing completion i
Function during SI Functional worked. Equipment will be expected 12-31-79.
Test functionally tested prior to Mode 4.
Repair 1-TS-MS-lllA and B LER/R0 79-117 Repairs complete.
LER/R0 79-130 Reset RS and QS Timers LER/R0 79-135 All timers listed in Expect completion Tech Spec Table 4.8-1 will 12/31/79.
be reset. Partially complete.
Quadrant Power Tilt - Inspect LER/R0 79-127 Rodlets were inspected.
No startup restraint.
I Rodlets Package ready for NRC review.
Inspect and Repair #2 Reheat LER/R0 79-126 Repair complete.
No startup restraint.
Right Steau Stop Valve will be tested.
i FI-1485 Inoperable - Repair LER/R0 79-115 Repairs complete.
Isolation Valves i
Repair 1-RS-P-3A Seal Leak LER/R0 79-78 Repairs Complete.
Diesel Generator Muffler LER/R0 79-5 DC-79-S14 field work complete j
Modification and Technical Review complete ay SNSOC.
NRC has com ted nackage for review (Ki Feedwater Held Inspections IEB 79-13 Complete - satisfactory.
e
NORTH ANNA UNIT 1 REFUELING OUTAGE REQUIREMENTS _
ITEM
~
SOURCE STATUS REMARKS Stagnated. Borated Oxygenated IEB 79-17 Conducting visual inspections.
Systems Inspection 1
24 Hour Run of Emergency IEB 79-23
~
Testing completed 12-21-79.
Diesels Revise Eme.gency Operating IEB 79-06 Response Complete.
Procedures Vepco letter Ser. No. 709A AFW Pump Run NRR letter of 09-28-79 Kotor drilen pump runs complete.
Llill complate turbine driven pump run in Mode 3.
AFW Valve Lineup Independent NRR letter of 09-28-79
/alve lineups revised Verification - Procedure to require independent verification.
Natural Circulation V'epco letter Ser. No. 796 Im..'uded in revised emergency Cooling Procedure of 11-26-79 procedures.
Valve and Operator IEB 79-14 DC-79-S74 known field Weight Verifications aork will be complete about 01-01-80.
North Anna September 25, 1979 NRC letter of 09-28-79 Response complete 11-26-79.
Event 17 Questions Service Water to Charging LER/R0 79-8 DC-79-S09 field work complete Pumps Modification and Technical Review complete by SNSOC.
NRC review complete Secondary Chemistry Amendment to NPF-4 Procedures complete.
Control s..
a m-
,,,, ogi u
o n
.um.
i I
r During a review of system operation following the plant trip at North Anna Power Station Unit 1 on September 25, 1979, certain systems were found to operate in a mannerin consistent with the Final Safety Analysis Report (FSAR).
Two areas of concern were discovered.
First, protective functions not l
going to completion following reset of a safeguard signal, and second, safe-guards equipment automatically returning to the nonsafety mode following reset of the safeguards actuation signal.
l This was reported to the NRC in LER 79-141.
l l
The following systems have been or will be modified prior to Unit 1 startup from the present refueling shutdown:
1.
Control Room Air Operated Dampers (AOD).
Prior to the modification the normally open A00's would close on receipt of a Safety Injection (SI) signal and reopen when the SI signal was reset.
The system will be modified such that the SI signal will be " sealed in" and the dampers must be reset by a separate reset switch.
2.
Iodine Filter Bank Air Operated Dampers.
Prior to the modification the A0D's would divert air to the filter banks on receipt of a Containment Depressurization Actuation (CDA) signal and would return to the nonsafety position when the CDA signal was reset.
The system will be modified such that the CDA signal will be
" sealed in" and the dampers must be reset by the control switch.
3.
Safeguards Area Air Operated Dampers. Prior to the modification, the A0D's would divert air to the filter banks on receipt of a Containment Depressurization Actuation (CDA) signal and would return to the non-safety position when the CDA signal was reset.
The system will be modified such that the CDA signal will be
" sealed in" and ~the dampers must be reset by the control switch.
4.
Inside/Outside Recirculation Spray Pumas.
Prior to the modifica-tion a CDA signal would start these ptsps following a time delay, should the CDA signal be reset before the expiration of the time delay the pumps would not start. The system will be modified such that the CDA signal will be " sealed in" and the centrol switchs for the pumps must be reset to prevent operation of the system.
5.
Containment Recirculation Cooling Fans.
Prior to the modification the fans would trip on receipt of a CDA signal and would restart when the CDA signal was reset. The system will be modified such that the fans will not restart when the CDA signal is reset.
}b9b
g 1
The following systems are not going to be modified during this refueling shutdown.
Design modifications for some systems will be implemented pending further study. Procedures will be modified se that plant safety will not be affected.
I' 1.
Service Water to Recirculation Spray Heat Exchanger Radiation Monitoring Sample Pumps.
At present a CDA signal will start these pumps following a time delay.
Should the CDA signal be reset before the expiration of the time delay the pumps will not start.
A modification shall be implemented to correct this problem.
After this modification, the signal will.go to completion unless CDA signal is reset and control switch is placed in the "STOP" position.
Until the change is implemented, a precaution will be added to station procedures stating that reset of CDA should not be accomplished until the control switch for the sample pumps are placed in the " START" position.
2.
Control Rod Drive Cooling Fans.
At present a CDA signal will stop the fans. Once the CDA is reset, the previously operating fans (three maximum) would restart.
A modification shall be implemented to torrlict this problem.
After this modification, the fans will remain " locked out" following CDA until the CDA signal is reset and a switch for the individual fan is reset.
Until this design change is implemented, a precaution will be added to station procedures stating that reset of CDA should not be accomplished until the control switches for the control rod drive fans are placed in the "0FF" position.
i 3.
Turbine Driven Auxiliary Feedwater Pump Steam Supply Valves.
At present an SI signal will open these valves to admit steam to the auxiliary feedwater pump. When the SI signal is reset the SI signal to the valves is also reset. The valves remain open because the main feedwater pumps (which were previously tripped by the SI signal) provide the open signal.
}
An additional " seal in" will be added to the valve control circuit such that when SI is reset the valve will remain open regardless of the status of the main feedwater pumps.
4.
Service Water Supply to Containment Air Cooling Coils (MOV-SW110A,B,MOV-5W114A,B,TV-SW101A,B).
The above valves will close upon receipt of a CDA signal, 1696 uB3
i should the service water mode selector switch be in the
" service water" position. When the CDA signal is reset, the valves will reopen. The cooling coils are: normally cooled by chilled water (CD).
Since the service water mode of containment cooling has not and is not presently planned to be utilized, the valves should be closed and power removed.
Any use of this mode of cooling wculd have to be under strict administrative control.
\\
A precaution will be added to station procedures stating that the service water mode control switch should be in the
" NORMAL" position prior to reset of CDA.
5.
Air Removal to Containment (TV-SV102-1, TV-SV103).
The above trip valves are containment isolation valves. They are both normally closed and are opened upon receipt of a high-high radioactivity level from the main condenser air ejectors.
Normally, non-condensables from the condenser are venteo to the atmosphere out a high-high radioactivity level shifts the venting into the containment. A containment is:lation signal will close these valves.
Upon resetting the containment isola-tion signal, the valves will reopen if the condenser high-high radioactivity signal is still present. Since there is a very remote possibility of this situation developing (i.e. chances of both primary to secondary leak with a LOCA in the contain-ment are very slim), and since there is a check valve inside the containment which would still isolate the containment when required, no change to this system is planned.
t 1696 fl84