ML20205S112
| ML20205S112 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/31/1986 |
| From: | Mcdonald R ALABAMA POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8704060524 | |
| Download: ML20205S112 (31) | |
Text
_
A!ASAMA POWER COMPANY JO6EPH M. FARLEY NUCLEAR FIANT UNIT 1 - ANNUAL REPORT REQUIRED BY 10CrR50.59 Section 50.59 of Part 50, Licensing of Production and Utilization racilities, of the regulations of the United States Nuclear Regulatory consission, states that the holder of a license authorizing operation of a production or utilization facility my (1) make changes in the facility as described in the safety analysis report, and (2) make changes in the procedures as described in the safety analysis report, and (3) conduct tests or experiments not described in the safety analysis report, without prior commission approval, unless the proposed change, test or experiment involves a change in the technical specifications inerrporated in the license or an unreviewed safety question (as defined in 10CrR50.59).
1he licensee is required to maintain records of such changes, tests or experiments, and those records are required to include written safety evaluations which provide the basis for the determination that the changes, tests or experiments do not involve any unreviewed safety questions.
Brief descriptions and a sunnary of the safety evaluations of the changes, tests or experim.ents as descritel above, for the Joseph M. Farley Nuclear Plant Unit I which were completed in 1906, are provided in the following.
t h fh N P'DM 5 ,
t Tech fijne 1/2 I
<- 3
. Subj:ct: PCR/PCN 79-494 (B79-1-494)
Description:
Installed suction and discharge pressure gauges for both residual heat removal (RHR) pumps.
Safety Evaluation: n ose gauges are used only during RHR pump surveillance testing. Two normally closed l instrument valves isolate each pressure gauge at all times except when surveillance tests are in progress. These gauges will increase the accuracy l of the measurements taken during surveillance testing.
PORC Reuews PORC Meeting 1393, 5/23/85 l
Subject:
PCR/PCN 80-758 (SM 80-1-758) l
Description:
Supplemented the existing bulk gaseous hydrogen storage system with a liquid hydrogen storage system.
Safety Evaluation he installation of this system is in conformance with the criteria delineated in the FSAR for the existing gaseous hydrogen storage tanks.
PORC Review: PORC Meeting 1421, 8/13/85
Subject:
PCR/PCN 80-759 (Sit 80-1-759)
Description:
Supriemented the existing bulk gaseous oxygen I
storage system with a liquid oxygen storage system.
Safety Evaluation %e installation of this system is in conformance with the criteria delineated in the FSAR for the existing gaseous oxygen storage tanks.
PORC Review PORC Meeting 1421, 8/13/85 1
. - - _ . .~ .. . - -. . . - _ _ _ _ . - .-
?
Subj:ctt PCR/PCN 80-796-(S80-0-796)
Descriptions. Added a back-up battery / charger set-to each train of tha service water DC distribution system.
Safety Evaluation: This addition enhances plant safety by increasing the reliability and availability of the service water DC power system. ,
PORC Review: PORC Meeting 1292, 10/2/84
Subject:
PCR/PCN 31-1058 (S81-1058)
Description:
Relocated a fan from the exhaust ducts to the supply ducts of.switchgear rooms A and B in the Diesel Building and the Service Water Intake Structure.
( Safety Evaluation: 1his change will resolve the negative pressure problem without reducing the ventilation capacity or affecting the structural integrity of the buildings.
PORC Review: PORC Meeting 1028, 9/21/82 [
Subject:
PCR/PCN 82-1247 (S82-1-1247) i
Description:
Provided a means for handling hydrazine drums l outside the Auxiliary and Turbine Buildings.
, Safety Evaluation: This modification will reduce perse'nnel exposure l
to the hydrazine fumes, which are a suspected carcinogen, by relocating the hydrazine drums outside the Auxiliary and Turbine Buildings. The hydrazine piping that was added in the Auxiliary Luilding was seismically supported to prevent the failure of this line from adversely affecting any safety related equipment in the event of an earthquake. This modification will not affect the integrity or reliability of this system or any safety related system and thus the consequences or probability of an accident will not be increased.
PORC Review PORC Meeting 1402, 6/25/85 i
i
w ,
. Subjset: PCR/PCN'82-1301 (B82- -1301) -
Description:
' Relocated the existing nuclear-laundry facility,to -
the Unit 1 Drumming Room. %is change wcs' performed.because the previous location of the ,
laundry created'a low radiation-background which-interfered with personnel frisking while exiting the Auxiliary Building Radiation Controlled Area.
Also, the previous. location did not allow adequate.
room to place the required number of washers and dryers. .The relocation of the laundry required a revision to-Figure ~9.4-6 (Sheet 3) of.the FSAR to>
show new pressure differential indicators on the air handling units. Druming of dry active waste has been consolidated in the Unit 2 Druming Room.
Safety Evaluation: he change does'not involve an unreviewed safety question.
PORC Review: PORC Meeting 1417, 8/6/85
Subject:
PCN 82-1306 (S82-1-1306)
Descriptiori: Provided for the relocation of. service water flow switch FS580 which isolates steam generator blowdown on low service water dilution flow.
FS580 had been located in a service water valve box and was relocated to the main control room. ^
mis relocation facilitates testing of the flow switch and removes the danger of flooding which the flow switch faced in the valve box.
Safety Evaluation: The relocation of this flow switch will enhance the reliability of the plant and will not increase the probability or the consequences of any accident evaluated in the FSAR.
PORC Review: PORC Meeting 1583, 10/23/86
Subject:
PCR/PCN 83-1402 (B83-1-1402)
Description:
Installed temperature switches upstream of the-fire darpers-in the containment purge and exhaust ,
ducts to provide for the automatic shut off of containment purge supply and exhaust fans on_high temperature'so that the fire dampers would not have to operate against full system flow.
-Safety Evaluation: This change does not affect the system operation under normal conditions.
PORC Review: PORC Meeting 1499, 3/18/86 3
l i
. SubjIct: PCR/PCN 83-1403 (B83-1-1403)
Description:
Installed a temperature switch downstream of the fire damper to provide automatic shutoff of the non-radwaste area air supply fan on high temperature so that the fire dampers would not have to operate against full system flow.
Safety Evaluation: 'Ihis change does not affect the system operation
, under normal conditions.
PORC Review: PORC Meeting 1503, 3/28/86
Subject:
PCR/PCN 83-1430-(S83-1-1430)
Description:
Installed a flange on the #1 Waste Monitor Tank vent pipe.
Safety Evaluation: The installation of a flange on the #1 Waste Monitor Tank vent pipe will facilitate unclogging of the vent line.
PORC Review: PORC Meeting 1491, 2/20/86
Subject:
PCN 84-2643 (n84-1-2643)
Description:
Updated Table 10.3-4 of the FSAR to show a new material of construction for the shaft of the main steam isolation valves (MSIV's).
Safety Evaluation: Based on the certification provided by the vendor (Atwood and Morrill) the modification performed by this design change will not affect the operability of the MSIV's.
PORC Review: PORC Meeting 1580, 10/14/86 l
l
)
I 2
4
. Subj; cts PCR/PCN 84-2702 (S84-1-2702)
Description:
Replaced the tubing downstream of the steam dump warming line isolation valves with stainless steel piping.
Safety Evaluation: The steam dump system is not required for safe shutdown of the plant. However, failure of this tubing could render portions of the steam dump syn. tem inoperable, which could affect plant startups or shutdowns when the steam dumps are in operation. By utilizing stainless steel piping, this design makes such a failure less likely.
PORC Review: PORC Meeting 1432, 9/12/85
Subject:
PCR/PCN 84-2757 (B84-1-2757)
Description:
Provided a display for the new Gamma-Metrics neutron monitor on the main control board.
Safety Evaluation: The display of the new Gamma-Metrics neutron monitor in the main control room will satisfy Reg.
Guide 1.97 and APCo comnitments in the Reg. Guide 1.97 compliance report.
PORC Review: PORC Meeting 1438, 10/1/85
Subject:
PCR/PCN 84-2759 (B84-1-2759)
Description:
Replaced the existing electronic indicator for the component cooling water (CCW) heat exchanger inlet flow with a differential pressure flow indicator for local indication. Also, added displays in the main control room.
Safety Evaluation: This design change will replace the existing indicator with a qualified indicator and provide displays in the main control room. This will satisfy Reg. Guide 1.97 and the APCo commitments in the Reg. Guide 1.97 Compliance Report.
PORC Review: PORC Meeting 1445, 10/22/85 5
... l l
Subject:
PCR/PCN 84-2762 (B84-1-2762)
Description:
Provided remote indication in the control room of radioactive liquid waste tank levels and waste gas decay tank pressure.
Safety Evaluation: his design change satisfies the APCo comitments-in the Reg. Guide 1.97 Compliance Report.
1 PORC Review: PORC Meeting 1441, 10/8/85 i
Subject:
PCR/PCN 84-2864 (B84-1-2864)
Description:
Partial modification to the radiation access-control area.
Safety Evaluation: he existing radiation access control area is congested and not utilized efficiently. his modification streamlines ingress, egress and personnel frisking. ..It provides a briefing area
, for radiation controlled area jobs. It separates.
j the existing hot toilet-into separate men's and women's restrooms and showers. It provides a connecting doorway between the Unit 1 and Unit 2 Filter Hatches Rooms in order to separate men's j and women's protective clothing dressout locations.
! ?
PORC Review: PORC Meeting 1398, 6/11/85 PORC Meeting 1452, 11/12/85
Subject:
PCR/PCN 84-2914 (B84-1-2914)
Description:
Provided for the replacement of service water piping having 2" and smaller diameters with stainless steel piping. his is intended to
, reduce the amount of corrosion in this piping.
4
%e design also provides for placing isolation valves on the supply and discharge headers of-various pump and room coolers in the plant.
l Safety Evaluation: Based on design calculations, these modifications-have a negligible effect on system performance.
PORC Review: PORC Meeting 1569, 9/18/86 PORC Meeting-1578, 10/9/86 PORC Meeting 1579, 10/13/86 7
I i
i 6
i
~ , . . . _ - _.,..s. . _ . _. . _ ~ .-_m , __w :..-.__. y , , , , , , ._._.7 ...m. , p.., , , , _ , , . . . ,,
Subjnct: PCR/PCN 84-2989 (S84-1-2989)
Description:
Assigned Total Plant Numbering System (TPNS) numbers to the presently unnumbered drain valves in the instrument air system.
Safety Evaluation: Drawing change only.
PORC Review: PORC Meeting 1387, 5/7/85
Subject:
PCR/PCN 84-2990 (B84-1-2990)
Description:
Added manual isolation valves in main steam bypass headers B and C downstream of bypass valves QV003E and QV003F.
Safety Evaluation: Installation of manual valves in B and C main steam bypass headers will help expedite secondary system heatup during plant startup by allowing greater steam flow to the Turbine Building.
Installation of the isolation valves will allow greater operating flexibility during startup.
PORC Review: PORC Meeting 1522, 5/13/86
Subject:
PCR/PCN 84-3018 (B84-1-3018)
Description:
This design change modified concrete block wall ICBW-34. The modification provided for external bracing of the wall with steel supports. In addition, a portion of the block wall was removed.
Safety Evaluation: New configuration meets the requirements of IE Bulletin 80-11.
PORC Review: PORC Meeting 1576, 10/7/86 7
Subj;ct: PCR/PCN 84-3022 (B84-1-3022)
Description:
Installed thermal liner assemblies in the main feedwater lines for steam generator B.
Safety Evaluation: Installation of the thermal liner assemblies at the steam generator feedwater nozzles will minimize the probability of cracking in the region of the pipe to nozzle weld. Thermal-hydraulic and stress evaluations have been performed to confirm the acceptable design of the assemblies.
PORC Review: PORC Meeting 1559, 8/21/86
Subject:
PCR/PCN 85-3121 (B85-0-3121)
Description:
Upgraded the Service Water Intake Structure microwave intrusion detection system.
Safety Evaluation: This upgrade will increase the effectiveness of the system and improve the ability of the system to detect unauthorized entry to the Service Water Intake Structure.
PORC Review: PORC fleeting 1452, 11/12/85
Subject:
PCR/PCN 85-3151 (S85-0-3151)
Description:
Provided a new tie-in to the existing potable water system to supply potable water to the new Computer Building. Also, provided a new fire main that ties into the existing fire protection system to supply water to the new Computer Building sprinkler system.
Safety Evaluation: The potable water system provides drinking water throughout the plant. This system is not safety related and has no effect on plant safety. The fire protection system provided for the new Computer Building meets NFPA 24.
PORC Review: PORC Meeting 1423, 8/20/fs5 8
Subj;;ct: PCR/PCN 85-3183 (B85-0-3183)
Description:
Plugged one floor drain and two equipment drains in the Dosimetry Lab (Room 461). ,
Safety Evaluation:- hese drains are no longer required as a result of an earlier modification to the Dosimetry Lab under PCN 84-2864.
PORC Review: PORC Meeting 1446, 10/23/85
Subject:
PCR/PCN 85-3183 (S85-0-3183)
Description:
Relocated two sprinkler heads and added two sprinkler heads on system 1A-52 in room 456 of the Auxiliary Building.
Safety Evaluation: he modification of the sprinkler system will enhance the sprinkler coverage of the newly modified storage / record area. his modification does not degrade the capability of the plant fire protection system.
PORC Review: PORC Meeting 1474, 1/8/86
Subject:
PCR/PCN 85-3194 (B85-1-3194)
Description:
Installed a Combustion Engineering (CE) heated junction thermocouple system as a reactor vessel level measuring system. his installation required modifications in the upper internals assembly, on the reactor vessel head, and arme the reactor vessel head.
Safety Evaluation: Meets the APCO comitment to NUREG 0737.
PORC Review: PORC Meeting 1569, 9/18/86 9
Subj:ct: PCR/PCN 85-3219 (B85-1-3219)
Description:
Upgraded the existing Post Accident Radiation Zone maps to reflect plant conditions.
Safety Evaluation: This upgrade satisfies a commitment made to the NRC in June 1984. Additionally, this will allow accurate decision-making in the event of a radiological emergency.
PORC Review: PORC Meeting 1531, 6/5/86
Subject:
PCR/PCN 85-3230 (B85-1-3230)
Description:
Provided for the rerouting and connection of the remote gas septum tubing to the local gas collection bomb and septum in the post accident sampling system.
Safety Evaluation: This modification will give a more representative sample of the gas in the gas collection bomb.
PORC Review: PORC Meeting 1522, 5/13/86
Subject:
PCR/PCN 85-3243 (S85-1-3243)
Description:
Revised drawings to show that the single line formed by the pressurizer steam, pressurizer
quid, and the reactor coolant hot leg sample lc os is routed to the volume control tank. This line previously had been routed to the letdown-line upstream of the demineralizer inlet.
Safety Evaluation: This revision was required to ensure the ability to obtain representative RCS, RHR and ECCS sump samples with letdown isolated.
PORC Review: PORC Meeting 147.7, 1/16/86 l
l l
10
Subj:;ct: PCR/PCN 85-3286 (S85-1-3286)
Description:
Added an additional branch of sprinklers to existing sprinkler system 1A-119 and realigned existing smoke detection systems to provide '
adequate coverage for the CCW pumps. This change is required due to Kaowool wrapping of cable trays above CCN pumps 1A, 1B, and 1C which is obstructing the fire protection sprinkler system.
Safety Evaluation: The modifications to the sprinkler and smoke detection systems will improve the coverage and responsiveness of the fire protection afforded the CCN pumps and will not degrade the protection and detection for other areas already covered by the systems.
PORC Review: PORC Meeting 1459, 12/3/85
Subject:
PCR/PCN 85-3350 (S85-1-3350)
Description:
Added a test line which tied into both trains of the containment spray system, so that both containment spray check valves as well as the refueling water storage tank check valve could be tested.
Safety Evaluation: During normal operation, the test line will not be used and is completely separated from the containment spray system.
PORC Review: PORC Meeting 1524, 5/20/86 1
11
Subject:
PCR/PCN 85-3368'(S85-1-3368)
==
Description:==
Deleted the Steam _ Generator Blowdown automatic-trip from the blowdown sampling system radiation monitor (R-19).
Safety Evaluation: Steam Generator Blowdown is'not ' required to-isolate automatically on an R-19 signal since blowdown isolates on an R-23A signal and the blowdown effluent isolation valve closes automatically on an R-238 signal.
PORC Review: PORC Meeting 1499, 3/18/86
Subject:
PCR/PCN 85-3373 (S85-1-3373)
==
Description:==
Deleted isolation valve N1G24V089 in the steam generator blowdown processing system drawing to reflect the existing plant . condition. This valve wns removed during a previous. design change but-the drawing was not revised to reflect this cnange.
Safety Evaluation: Drawing change only.
PORC Review: PORC Meeting 1559, 8/21/86 1
12 l
- SubjIct: PCR/PCN 85-3379 (B85-1-3379)
Description:
Modified the solid state protection system (SSPS) output relay test panel to ensure detection of a previously potentially undetectable test circuit failure.
Safety Evaluation: This change assures that plant operators and technicians will be aware of SSPS relay test switch failures which could affect system operation. This change has no impact on the test circuits which confirm system integrity and operability.
PORC Review: PORC Meeting 1511, 4/17/86
Subject:
PCR/PCN 85-3458 (S85-1-3458)
Description:
Assigned TPNS numbers to the vent and pressure switch isolation valves in the air supply line tc the turbine driven auxiliary feedwater (nwfW) pump steam admission valves. Also revised the i TPNS numbers for check valves in the same air supply line.
Safety Evaluation: Drawing change only.
l PORC Review: PORC Meeting 1522, 5/13/86 '
PORC Meeting 1557, 8/14/86 13
Subjects. PCR/PCN 85-3459 (S85-1-3459)
Description:
Deleted differential pressure indicator N1G21PDI2909 and its root valves from the FSAR because they do not exist in the plant. A figure in the FSAR shows this PDI as being installed across the waste evaporator condensate tank inlet filter.
Safety Evaluation: his PDI is not required since separate inlet and outlet pressure indicators are installed to allow determination of the differential pressure across the waste evaporator condensate tank inlet filter.
PORC Review: PORC Meeting 1493, 2/25/86 I
l
Subject:
PCR/PCN 85-3460 (S85-1-3460) i
Description:
Revised drawings to reflect the proper position
- for two valves in the waste gas processing system.
i n e drawings were revised to show valve 01G22V216 i (pressure transmitter PT-1066 isolation) as open
{ and valve Q1G22V035 (waste gas compressor drain to 4
the gas decay tank header) as closed.
Safety Evaluation: Q1G22V216 is required to be open for proper
} operation of pressure transmitter PT-1066.
g Q1G22V035 is required to be closed for proper ,
- operation of the waste gas compressors.
f l PORC Review: PORC Meeting 1499, 3/18/86 i
i
Subject:
PCR/PCN 85-3461 (Se5-1-3461) i
Description:
Deleted differential pressure indicator NIE21PDI2911 and its root valves from the FSAR l because they do not exist in the plant. A figure in the FSAR shows this PDI as being installed i across the recycle evaporator concentrates filter.
i Safety Evaluation: his PDI is not required since separate inlet and i outlet pressure indicators are installed to allow J
' determination of the differential pressure across the recycle evaporator concentrates filter.
PORC Review: PORC Meeting 1493, 2/25/86 1
14 i
s
, _ . , _ _ _ , , ,.,,my- ,,_y.,vry, --,., ..-., _, -
-y y , , _ , . ..-,m.
Subj;ct: PCR/PCN 85-3462 (S85-1-3462)
Description:
Revised drawings to reflect the correct operating alignment for the seal water return to the volume control tank (VCT) isolation valve. This valve should remain in a " locked closed" position during normal operation to preclude inadvertent operation of the valve.
Safety Evaluation: The seal water return to the VCT is an alternate path and it would be used only when the seal water return isolation valve is inoperable. Therefore, changing this valve from normally closed to normally " locked closed" does not impact the safety of the plant, j PORC Review: PORC Meeting 1499, 3/18/86
Subject:
PCR/PCN 85-3473 (S85-1-3473)
Description:
Revised drawings to show that the reactor coolant drain tank (RCDT) recirculation orifice outlet isolation valve and the RCUT pump discharge valves are in a " locked throttled" position instead of in the "open" position.
Safety Evaluation: This change will prevent pump run-out and allow sufficient pump discharge head for flow through the demineralizer and filter to the recycle holdup tank.
PORC Review: PORC Meeting 1499, 3/18/86
Subject:
PCR/PCN 85-3482 (S85-0-3482)
Description:
Revised drawings to reflect the correct valve line-up for operation of the waste gas processing system and the main steam system.
Safety Evaluation: Drawing change only.
PORC Review: PORC Meeting 1520, 5/6/86 15
Subj:ct: PCR/PCN 86-3634 (S86-1-3634)
Description:
Revised the Auxiliary Building floor drain drawing to show the installation of a section of A106 grade B pipe in place of A53 grade B pipe.
Safety Evaluation: Drawing change only. ;
PORC Review: PORC Meeting 1595, 11/11/86
Subject:
PCR/PCN 86-3647 (S86-1-3647)
Description:
Rerouted the 18 diesel generator control and starting air piping to provide positive venting of the rack boost cylinder. The rack boost cylinder ensures that fuel is supplied to the diesel engine during the early stages of engine starting.
Safety Evaluation: Positively venting the rack boost cylinder will improve plant operation and reliability.
PORC Review: PORC Heeting 1595, 11/11/86
Subject:
PCR/PCN 86-3648 (S86-0-3648)
Description:
Rerouted the 1-2A diesel generator control and starting air piping to provide positive venting of the rack boost cylinder. The rack boost cylinder ensures that fuel is supplied to the diesel engine during the early stages of engine starting.
Safety Evaluation: Positively venting the rack boost cylinder will improve plant operation and reliability.
PORC Review: PORC Meeting 1595, 11/11/86 16
Subj;ct: PCR/PCN 86-3675 (B86-1-3675)
Description:
Installed thermal liner assemblies in the main feedwater lines for steam generators A and C.
Safety Evaluation: Installation of the thermal liner assemblies at the steam generator feedwater nozzles will minimize the probability of cracking in the region of the pipe to nozzle weld. Thermal-hydraulic and stress evaluations have been performed to confirm that the design of the assemblies is acceptable.
This modification does not involve an unreviewed safety question.
PORC Review: PORC Meeting 1559, 8/21/86
Subject:
PCR/PCN 86-3753 (B86-1-3753)
Description:
Installed flex hose assemblies in the air supply lines to the actuator and test cylinders on the MSIV's.
Safety Evaluation: Flex hoses between the instrument air piping and the MSIV's allows the main steam piping to move freely without endangering the instrument air piping.
PORC Review: PORC Meeting 1569, 9/18/86 .
Subject:
PCR/PCN 86-3869 (B86-1-3869)
Description:
During the Unit 1 cycle 7-8 refueling outage, the rotating assembly for the lA Motor Driven Auxiliary Feedwater (MDAEW) pump was replaced.
Test data showed that the repaired pump provided a greater flow rate than the pump had provided originally.
Safety Evaluation: This design change considered all the concerns raised by the increased flow rate to evaluate the potential impact of this increased flow on system performance and associated containment pressurization and teactor vessel safety analyses.
This design change also provided information on items that could be affected by a reduced reactor coolant system temperature.
PORC Review: PORC Meeting 1599, 11/17/86 PORC Meeting 1603, 11/20/86 17
Subjtet: FNP-1-AOP-33.0 Revision 0, TCN OA
Description:
Corrected the FSAR discussion concerning the isolation of the steam generator blowdown (SGBD) system upon receipt of a high radiation signal..
Contrary to information currently shown in the i FSAR, SGBD isolation valves 7614 A, B and C do not close upon receipt of a high radiation signal from radiation monitor R-19. R-19 isolates only the-4 SGBD sagling system.
Safety Evaluation: SGBD is isolated upon receipt of a high radiation signal from R-23A and the SGBD discharge to the environment is isolated upon receipt of a high radiation signal from R-23B.
PORC Review: PORC Meeting 1490,'2/18/86
Subject:
FNP-0-AP-3 Revision 7- [
3
Description:
Revised procedure FNP-0-AP-3.to show.the current plant organization. This revision affected two
} items shown in the FSAR:
! 1) The requirement for the Assistant General 1 Manager-Plant Support to have a senior reactor operator's license or the experience ,
i and training required for this license was-deleted.
- 2) The qualification requirements for the Health Physics Supervisor were changed to be consistent with Regulatory Guide 1.8.
t j Safety Evaluation: Changing the qualification requirements for these
! individuals constitutes an administrative change
] only, i
PORC Review: PORC Meeting 1525, 5/22/86 .
i i
r i
i
! 18 i
. _ , _ - ~ _ ._, _ _ - . _ , , _ _ . . , _ _ _ _ . _
, . ,_ _, .,m_
Subjrct: FNP-0-AP-33 R2. vision 8
Description:
Clarified requirements for qualification of inspection, examination and testing personnel.
his improved compliance with connitments and allows management enhanced flexibility in establishing requirements.
Safety Evaluation: h is change is for clarification purposes and is administrative in nature.
PORC Review: PORC Meeting 1536, 6/20/86
Subject:
ENP-1-CCP-301 Revision 1, 'ICN 1A
Description:
Provided for the increase and control of the circulating water cycles of concentration by reducing the blowdown rate and periodically closing blowdown. The FSAR states that the circulating water system will have a continuous blowdown in order to keep the solids content in the circulating water within acceptable limits.
Safety Evaluation: The solids content of the circulating water would still be maintained within acceptable limits.
Supporting data has shown that the corrosion rate of the water boxes and cooling towdr piping should decrease with higher cycles of concentration.
PORC Review: PORC Meeting 1499, 3/18/86 19
SubjIct: FNP-1-CCP-329 Revision 0
Description:
Provided a method to add small quantities of sodium hydroxide (NaOH) to the containnent spray system spray additive tank (SAT). The FSAR does not address a method for adding small quantities
- of NaOH to the SAT.
Safety Evaluation: he proposed NaOH addition system was evaluated for compatibility with NaOH and to ensure that allowable pressure within the addition system would not be exceeded. Operability of the SAT was not affected.
PORC Review: PORC Meeting 1609, 12/21/86
Subject:
FNP-0-CCP-708, TCN 1A, 1C, ID and IE
Description:
Provided for the continuous chlorination of the Unit 1 service water system during a test period to determine if improved control of Corbicula can be obtained without an adverse effect on plant safety or the environment. We chlorination is to be performed using sodium hypochlorite. 1CN 1A was issued to start the initial stage of the program. TCN 1C was issued to increase the chloride concentration and document the approval
- from the State of Alabama to increase the '
allowable concentration at the point the chlorinated water enters the river. TCN ID extended the use of sodium hypochlorite for chlorination of the service water system during the entry of modes 1 and 2, and continued addition through 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 28 November 1986. We objective of this extension was to achieve 100%
adult Corbicula mortality. TCN lE further extends the chlorination program. This program was conducted on Unit 1 only.
20 i
i
.= - - . . -. . -. . .
Safaty Evaluation: .For the initial attge of the chlorination program, the unit was shutc,own. Werefore, cooling water requirements were at a minimum and the unit was in the best position for components to be removed from service and cleaned if flow restrictions I occurred. It was verified that the program could '
be continued without adversely affecting safety
-related heat exchangers before entry into a higher-mode. During the latter stage of the program, any reduced component performance resulting from fouling by Corbicula during modes 1 and 2 could have been handled through normal plant. procedures.
Increased. vigilance was maintained on critical components to ensure early detection of.any flow .
restrictions. Sodium hypochlorite addition can be quickly terminated if deemed necessary by plant operations.
PORC Review: PORC Meeting 1586, 10/27/86 PORC Meeting 1592, 11/6/86 PORC Meeting 1597, 11/15/86 PORC Meeting 1606, 11/26/86
Subject:
ENP-0-EIP-26 Revision 18
Description:
Revised the ENP Emergency Plan to require notification to. state officials within fifteen minutes of declaration of any emergency class.
Previous evaluations had concluded that notification within one hour of the declaration of a Notification of Unusual Event was sufficient.
Safety Evaluation: The fifteen minute notification will allow additional response time for the state agencies and provide for consistency of the Emergency Plan.
with 10CFR50, Appendix E.
PORC Review: PORC Meeting 1615, 12/17/86
Subject:
FNP-1-ETP-1013 Revision 0
Description:
Provided a means of cooling down steam generators ,
lA, 1B and 1C. This method is not described in l the FSAR. The procedure was written for testing in Mode 5 when-the safety related systems utilized ;
in the test are not required to be operable.
Safety Evaluation: This procedure is sufficient to provide adequate guidance to prevent or mitigate any malfunction ,
that could occur to overpressurize a steam-generator. ,
PORC Review: PORC fleeting 1572, 9/30/86 1
l 21
Subj;ct: ENP-0-ETP-1014 Revision 0
Description:
Provided for flushing the steam generator tube support plates. The tube support plate flushing process is a series of depressurization cycles used to optimize removal of chemicals from areas
'of restricted flow such as the region between the tube support plates and the tubes.
Safety Evaluation: The use of the tube support plate flushing procedure will not adversely affect the safe operation of the plant in general, and the steam generator tube bundle integrity in particular, and does not represent an unreviewed safety question with one, two or three steam generators being flushed at one time. .
1 PORC Review: PORC Meeting 1520, 5/6/86
Subject:
FNP-1-PMP-1065 Revision 0
(
Description:
Provided for placing temporary scaffolding in i containment in order to perform a thernal expansion test on feedwater piping movements due to plant heatup. Certain portions of feedwater piping insulation were also removed to enable whip restraint gap measurements to be made.
]
t Safety Evaluation: The scaffolding will be erected and removed at 30
+ 5% power under administrative control.
l PORC Review: PORC Meeting 1601, 11/18/86
Subject:
FNP-1-RCP-611 Revision 2, TCN 2A
Description:
Provided a method of sampling the volume control tank (VCT) via tygon tubing, a sample bomb, and a vent bottle. The VCT sample flow cannot be established because a spring-loaded check valve in the sample line requires 80 psig to open but the normal operating pressure of the VCT is only 20 psig.
Safety Evaluation: This temporary change is needed until the check va]ve is replaced with a 5 psig spring. Personnel will be protected during sampling by filters installed on the vent bottle. Appropriate Health Physics coverage will be provided. Hydrogen gas concentrations will be limited by supplying nitrogen to the vent bottle during purging.
Pressure and temperature limits of the various components were considered and determined to be adequate.
PORC Review: PORC neeting 1573, 10/2/86 22
Subj;ct: FNP-1-STP-605.2 Revision 6
Description:
Updated an FSAR reference to the IEEE standard for
- battery operability tests. The FSAR references-IEEE 450-1972. However, the correct reference is-IEEE 450-1980, as stated in the bases for Technical Specification 3/4.8.
Safety Evaluation: Administrative change only.
PORC Review: PORC Meeting 1578, 10/9/86
Subject:
MD 83-447 Revision 1 MD 85-1140 Revision 1 MD 86-1614
Description:
Added an isolation valve and a Chicago fitting to each of the condensate pump suction drain lines to facilitate the initial boric acid soak of the steam generators. Sufficient boric acid is added by vacuum drag to bring the steam generator concentration to about 50 ppm. These valves and fittings are removed at the conclusion of the boric acid soak. During normal operation boric acid is maintained via the auxiliary feed chemical addition pumps.
Safety Evaluation: The condensate system is not necessary for safe ,
shutdown of the plant.
i i
PORC Review: PORC Meeting 1596, 11/14/86 (MD 1614)
PORC Meeting 1613,12/16/B6 (MD's 447 and 1140)
Subject:
MD 86-1490 Revision 1
Description:
Installed 3/8" stainless steel tubing with isolation valves on the condensate pump discharge 1 drain lines. The FSAR shows these drain lines as being capped. This installation provides sample points for a corrosion product transport study.
Safety Evaluation: The condensate system is not necessary for the safe shutdown of the plant.
PORC Review: PORC Meeting 1586, 10/27/86 2
l I
23 I
I - - - - --.-
.- - ~ ~ . . - .._. .. . . - . - . . -. - - . - .. ~ - . . - - - . .
SubjIcts im 86-1504
Description:
Added sample points to the condensate pump discharge and suction piping as well as the combined discharge header piping. Also, replaced -
the carbon steel portion of the combined condensatepumpdischargeheadersangleline-to the secondary chemistry lab with 3/8 stainless steel tubing.
Safety Evaluation: Additional sample points in the condensate system will aid in locating inleakage in condensate I
l- system components which causes high dissolved oxygen levels. Also, the long length of the ;
combined header sample line is depleting the oxygen in the sample causing non-representative results. Se replacement with stainless steel will result in much more accuracy in dissolved oxygen measurement. L PORC Review: PORC Meeting 1579, 10/13/86
Subject:
- MD 86-1560
Description:
Removed the existing solid plug from a socket fitting on the number one and number three main turbine stop valves and installed fittings for instrumentation required for the turbine ,
performance test. Double valve isolation is preiided.
Safety Evaluation: This change does not represent any reduction in plant safety..
PORC Review: PORC Meeting 1599, 11/17/86 ;
Subject:
MD 86-1574
Description:
Modified the intended function of the Access ,
control Area air handling unit to provide adequate ;
cooling to the Dosimetry Lab pending completion of the Access control Modification per PCN 85-1-2864.
Safety Evaluation: W e FSAR (paragraph 9.4.2.3.3) states that the Access control Area HVAC system is not an Engineered Safeguard System and no credit is taken for its operation in analyzing the consequences of .
any accident. The results of an engineering i evaluation showed that flow from the non-radwaste l area to the radwaste area would be maintained.
PORC Review: PORC Meeting 1574, 10/2/86 l 1
24 l
1 Subj::ct: MD 86-1591
Description:
Temporarily defeated the steam generator blowdown [
(SGBD) low dilution flow trip to allow SGBD.
operation with the dilution flow transmitter out ,
of service for a design change. '
j- Safety Evaluation: No safety concern existed since the reactor coolant system was depressurized at this time and ,
4 minimal risk of a primary to secondary leak ,
existed. SGBD flow was needed following 4
completion of work on the steam generator ,
- anti-vibration bars (AVB's). !
i compensatory measures were taken and the system j was restored to normal operation upon completion r
'. of the design change on the dilution flow j transmitter. ,
PORC Review: PORC Meeting 1585, 10/29/86 i
j
Subject:
MD 86-1622
]
Description:
Removed a carbon dioxide (CO,) bottle from the
< incore seal table. ;
4 Safety Evaluation: he use of CO purging for incore flux thimble cleaninghasfuendiscontinuedduetothe ,
probability that it contributed to a residue
- buildup in the tubes.
PORC Review: PORC Meeting 1606, 11/25/86 i
1 l
4 i
]
l l r
i
! \
i l
l i 1 1
25 i
! l
Subj:ct: Unit 1 Cyclo 8 Reload Safaty Evaluation
Description:
This safety evaluation forms the basis for licensing the Unit 1 Cycle 8 core design. A total of 4 Region 7, 18 Region 8, 74 Region 9, and 61 fresh Region 10 fuel assemblies are.used in the design. A total of 756 fresh wet annular burnable absorber rods are used in 49 clusters of 8, 12, 16 or 20 rods. The Region 10 fuel assemblies differ from the previous design in that they include chamfered fuel pellets, a reduced fuel rod helium backfill pressure, a modified fuel rod bottom end plug design, 49 plenum springs, and grid sleeves made from 304L stainless steel. All of the assemblies used in Cycle 8 have anti-snag grid designs.
The burnable absorber rods differ from past cycles in that they incorporate annular aluminum oxide-boron carbide (Al,0, - B C) absorber pellets contained within two concentric Zircaloy tubes with water flowing through the center tube instead of the current stagnant air-filled central tube and outer stainless steel clad containing borosilicate glass with B,0, absorber.
Safety Evaluation: Based on the Reload Safety Evaluation and the analyses performed by Westinghouse and Southern Company Services, Inc., this reload does not ,
involve any unreviewed safety questions.
l PORC Review PORC Meeting 1584, 10/24/86 l
Subject:
Description:
Changed the Emergency Plan to require notification l of state and local agencies within one hour of the declaration of a Notification of Unusual Event and within 15 minutes of the declaration of an Alert, Site Area Emergency or General Emergency. ,
safety evaluation: This change included no changes which would
, increase the probability or consequences of an l accident previously evaluated, no changes which would create the possibility of a new or different kind of accident from any accident previously l
evaluated and no changes which would involve an unreviewed safety question. Also, these changes
! do not decrease the effectiveness of the Emergency Plan.
l PORC Review: PORC tteeting 1492, 2/21/86 l PORC iteeting 1522, 5/11/86 26
subj:ct: Safsty Evaluation: Reduction of Riv3r Water Level
Description:
Approved the lowering of the elevation of. Jim Woodruff Reservoir to 74 feet MSL. This was done due to drought conditions which existed in the Chattahoochee River Basin.
Safety Evaluation: Allowing rivet level to fall to 74 feet MSL will not adversely affect river water pump opiration nor environmental concerns as previously evaluated in the FSAR.
PORC Review: PORC Meeting 1565, 9/5/86
Subject:
Safety Evaluation: Containment Calculated Peak Accident Pressure, PA (ES-85-495)
Description:
Provided revised values of containment peak calculated post-accident pressure and temperature.
This re-analysis included reduced amounts of heat input from the zirconium-water reacticn. Previous calculations had used overly conservative values for the zirconium-water heat input, the peak containment pressute was reduced from 48.4 to 48 psig and the peak temperature was reduced from 316 to 313'r.
Safety Evaluation: This calculation provides more realistic values. ,
No accident analysis is adversely affected.
PORC Review PORC Meeting 1555, 8/12/86 l
l l
27 j
Subject:
Safety Evaluation: Transfer of Control Rod Guids Tubes from Type A Cask to Type B Cask
==
Description:==
Approved tne transfer of control rod guide tubes to a different type of cask. During the Unit 2 fourth refueling outage, two irradiated control rod guide tubes were removed from the upper internals and placed inside a canister which was then placed in a Type A storage cask. Before these guide tubes could be shipped offsite for burial, they had to be transferred to a Type 3 shipping cask.
Safety Evaluation: The transfer of the control rod guide tubes from the Type A cask to the Type B cask is performed under vendor procedures.
PORC Review: PORC Meeting 1547,7/28/86
Subject:
G0-EIP-111 Rev. 13
==
Description:==
This procedure provides guidance for the activation of the Nuclear Generation Department emergency organization.
Safety Evaluation: This revision to the procedure revises the phone numbers listed for notification.
PORC Review: N/A
Subject:
G0-NG-38, Rev. O
==
Description:==
This procedure provides guidance for the steps required to ensure receipt inspections for General Office consigned services are properly performed and documented.
Safety Evaluation: This procedure provides guidance for receipt inspection of General Office consigned services by the General Office Nuclear Generation Department Staff.
PORC Review: N/A 28
Subject:
Nucler.- Op rations Review Board (NORB) Manual
Description:
This manual provides operating guidelines for all NORB activities.
Safety Evaluation: This manual provides guidance for the NORB to conduct independent reviews of safety-related matters.
PORC Review: N/A
Subject:
Operation Quality Assuran'ce Policy (0QAP)
Implementation List, Rev. 13
Description:
The OyAP Implementation List is a composite listing of administrative procedures responsible for assigning responsibilities in the Operation Quality Assurance Policy Manual.
Safety Evaluation: This revision to the 0QAP Implementation List is the result of changes in the Technical Support organization.
PORC Review: N/A
Subject:
Operation Quality Assurance Policy Manual, Rev. 24
Description:
This manual establishes the Quality Assurance Policy for the Farley Nuclear Plant.
Safety Evaluation: This revision incorporates organizational changes made to the of fsite nuclear support group.
PORC Review: N/A
Subject:
Safety Audit and Engineering Review (SAER) - AP Manual - Rev. 11
Description:
This manual provides administrative guidance for performing the duties of the SAER.
Safety Evaluation: This revision to the manual addresses changes made to the offsite support organization.
PORC Review: N/A 29 L _ - - - - _ _ _ - - - - - - - - - - - - - - _ - _ _ - - - _ _ - - - - - .-. --__ _ _ _ _ _ . - _ - _ . - - - -
Atbama Power Company 600 North 18th Street Post Office Box 2641 '
Birmingham. Alabama 35291-0400 '
Telephone 205 250-1835 nio V ce r sident '
the southem electic system 10CFR50.59 March 31, 1987 Docket Nos. 50-348 U. S. Nuclear Regulatory Commission ~
ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
Attached for your review is the annual report required by 10CFR50.59 for 1986. This report summarizas changes to the plant performed in accordance with the provisions of 10CFR50.59 for Joseph M. Farley Nuclear Plant Unit 1.
If there are any questions, please advise. -
Respectfully submitted,
' ALABAMA P0WER OMPA Y W
R. P.. Mcdonald ;
RPM / REM: dst ,
i Attachments cc: Mr. L. B.,Long Dr. J. N. Grace
.Mr. E. A. Reeves #
Mr. W. H. Bradford .
Y t !
\ \