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{{Adams
#REDIRECT [[DCL-87-270, 10CFR50.59 Annual Rept of Changes,Tests & Experiments 860323-870322]]
| number = ML20236N543
| issue date = 03/22/1987
| title = 10CFR50.59 Annual Rept of Changes,Tests & Experiments 860323-870322
| author name =
| author affiliation = PACIFIC GAS & ELECTRIC CO.
| addressee name =
| addressee affiliation =
| docket = 05000275, 05000323
| license number =
| contact person =
| document report number = DCL-87-270, NUDOCS 8711160220
| package number = ML20236N540
| document type = ANNUAL OPERATING REPORT, TEXT-SAFETY REPORT
| page count = 11
}}
 
=Text=
{{#Wiki_filter:. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ ,
  .c      .
,                                                            PG&E Letter No.: DCL-87-270                        ,
ENCLOSURE DIABLO CANYON UNITS 1 AND 2 DOCKET NOS. 50-275 AND 50-323 10 CFR 50.59 ANNUAL REPORT OF CHANGES, TESTS, AND EXPERIMENTS MARCH 23, 1986 - MARCH 22, 1987 1
Pacific Gas and Electric Company i
i 1
i i
i 8711160220 871109                                                                                    I PDR    ADOCK 05000275 R                  PDR                                                                              j i
i 16675/0052K
 
4
.                                                                                                            :r b
                                          -ATTACHMENT'l                                                                                      ,
FACILITY CHANGES FOR ANNUAL REPORT.                                                    '
                                                                                                                  ,,                              i March 23,'1986 - March 22, 1987 3+                r L
I .-    LIST OF. CHANGES                                                                                          "
q r                                        1. s ,
                                                                    'DCPP-Unit                    Change '            W E                        Sub.iect                          Acolicahility Identification                              13 j j
l'      Liquid Radioactive Maste Concentrator
                                                                                                                ~
        .                                                          y 10                        DCEd7t66R.0 I'N Condensate' Tanks Recirculation                                                        W          .J
                                                                                    .c                        y
: 2.      Convert Radioactive Maste                        .            .1,x2)          1' ' Ddh)31188R.'2
          -Concentrator.                                                      Qp-
: 3.      Install Radioactive Maste Processing                            1, 2 '            DC H-11674>R.2                          nw Media Filters                                                                                , . ..;                    .
: 4.      Convert Spent..RegenerantLReceiver Tanh to Standby Drain Receivers 1, 2              DCH-3NDirN.'2                          [Y
: 5.      Replace Reactor Co'olant Resistance                              1                  DC J-31961 R.0                1-Y Temperature Detectors.
                                                                                                                                        , a. <
: 6.    . Replace' Solenoid Valves of. Main Steam    i                  1, 2              DC J-35761 R.1.                            /'
Isolation Valves                                        '
DC J-36761 R.1
                                                                                                                                                ;i
  ;7..      Replace Steam Generator Feedwater Ring J-Tubes.
1                .DC'M-35476 R.0' d
s                                    e
  '8.      Containment Interior Paint Inventory g,      ,
1, 2l              DCMb7096R.4 DC M-28096 R.4 r-DC M-33052 R.4 DC H-34052 R.4
                                                                                                                                          'y' l"
(              >                                                                (:
: 9.    .Postaccident Monitoring Syst'em                                  1, 2              DC J-27357 R.3 (RG 1.97)'                                            '
DC J-27311 R.2 a                        DC J-28311 R.2
                                                                                                                              ,Q Ti;
: 10. Containment Mater Level Indication                              i                  DC J-35185 R.1                '?'      t j e                      .                                      ,
: 11. Auxiliary Steam Pipe Break Isolation                >
                                                                        ' 1 , 2,                DC M-33716 R.0                                      l i            DC M-34716 R.0 l
  .12. Replace Three Control Room Area                                  1, 2              DC A-35723 R.1                                    !
Doors 1667S/0052K                                                                                                                              !
                                                                                                                                                /
 
t
                                                                                                                                            .nf                t 1        og                                            -
                                                                                                  !i -
                                  .) '                                                          [ ,}                                *'
j-                                                                                    1 DCPP Unit            Change M
1                                                                                                      Sub1ect                                            Aeolicability Identification y                                                                                                                                        t
: 13.                Modify and Reinstall Lov\Denitty Spent                                                          1, 2          DC H-35152 R.1 Fuel Racks                                              a                    ,
DC H-38360 R.1 3' ,0                        14. -              Addition $tNsvSpentFuelPoolCooling                                                              1, 2          DC H-33785 R.2 4 yl; Pump                                                        ,                                                  DC H-34785 R.2  ;
: r.                                                  ' nu '
      -f; l
U jl5.                            Spent' Fuel Handling Brackets                                                                    1, 2          DC C-35696 R.0- i is.                        >
                                  ,9 :p '                                                    .f    d '                        ..
DC C-36696 R.0
  ' u,' a q 4                          .
e                                .
j' ] -                                              DC C-37442 R.0
  *'                                <l
* J. , y                                                                                                                                          DC C-38442 R.0 f'                                                                    DC H-33230 R.0
, ~ 'W
                                                                    ''9    '
                                  ,_.,                                                                                                                                            DC H-34230 R.1 2                                              n p                                          7                                                                                        . . ,
j t'                                            16.                Steam Generator BlowdowntSystem                                                    ?.
                                                                                                                                                            ,    'l        . DC H-35235 R.0    :
o                                                              Modification                                                                ,
                                                                                                                                                                          'l    ;
: 17.              . Add Bearing Lift System f$r LP J                                                                  !              DC H-15286 R.2  l WM '                                                      Turbine "C" Rotor Searing No. 8                                                                              '
0'                                    , .,
i 3 1Nk,RedundantCVd3Leh,dhwnFilter                                                                                        1              DC H-27132 R.2 O          's          .
(
: 19.                R?ccat                    Main Condenser. Hater Boxes                                            2              DC H-36329 R.0 W                          "t DC H-36536 R.0
                                                                                .y                                      y;
: 20.                Eire Water System ES cuth Site                                                                    1, 2          DC H-33127 R.4 a'                                                        '
    ,'                                                                            :1                              .,          ./
: 21.              . Backup Overcurrent Protaction for-                                                              'l '
DC E-3459 R.1
        ..''/-l                                                Containment Electrical (Penetrations                                                                              DC E-3941 R.1
                                'O!                                                                                        ;
DC E-5415 R.2 dl>  1. ~ , ' , /
i if DC E-7140 R.0
                                                                                        .-c                                                                                        DC E-11016 R.0    ;
i,,,                  ,
DC E-11426 R.0 s, (
4
)-                                        .y i
j 'l '
( ,
1 l
4
                .p s                                                    ,
H&                    's q y(r so-
    ; ,C t
l f.
,8 1667S/0052K                                                                                          i
 
1 ii                                                                                                j i
II. DISCUSSION OF' CHANGES-                                                            _
    ~ 1.      Liquid Radioactive Haste Concentrator Condensate Tanks Recirculation                :
l DCP# M-37166 Rev. 0 (Unit 1)
This change;has increased the diameter of the liquid radwaste recirculation piping to the process waste receiver tanks. This                        ,
modification increases the capacity of the liquid lradwaste processing system.              ,
            . Safety Evaluation Summarv l-The replacement piping was evaluated per the seismic and quality                      i assurance criteria in Regulatory Guide 1.143. Although the quantity of                i the liquid radwaste being recirculated to the waste receiver tank is                ;
increased, the: total amount of liquid radwaste within the radwaste                  '
system is not increased by this modification. Thus, the probability of an inadvertent release of radioactivity to the environment is not increased, nor are the radiological consequences of an unexpected release of radioactivity increased.
: 2.      Convert Radioactive Haste Concentrator DCP# M-31188 Rev. 2 (Units 1 and 2);
This change disconnected the radioactive waste concentrator to allow for its conversion to an additional boric acid concentrator at a later date. Removing the waste concentrator still leaves adequate liquid radwaste processing capabilities.
Safety Evaluation Summary Conversion of the waste concentrator still leaves redundant waste treatment flowpaths available within the radwaste processing system.
While decontamination factors for certain isotopes are lower for the remaining liquid radwaste treatment equipment, overall ability to treat waste to below 10 CFR 20 concentrations per Technical Specification                  ;
3/4.11 is not impaired under base load conditions.
: 3.      Install Radioactive Haste Processina Media Filters DCP# M-11674 Rev. 2 (Units 1 and 2)
This change installs media filters and associated piping, valves and instruments in the liquid radwaste system, along with piping
            . modifications for the existing radwaste ion exchangers, thereby improving the operation of the liquid radwaste system by adding additional filtering capability.                                                      1 S3fety Evtluation Summary The potential for release of radioactive material from the plant is not                ,
increased by this change, nor are the predicted releases of radioactivity from the plant due to an accident increased. The filter vessels and associated piping are designed in accordance with the standards in Regulatory Guide 1.143.
1667S/0052K                                                                                                                                  )
 
i
  ,e o        ,                                          .
: 14.    ' Convert Snent Reaenerant Receiver Tanks'to Stan'dhv Drain Receivers' DCP#.M-33500 Rev. 2 (Units-1-and-2)-
l LThis change modified:the liquid waste spent regenerant neutralization subsystem to allow the spent regenerant receiver tanks.also to be used
                        ' as backup equipment and floor drain receiver tanks.
i
                            -Safety Evaluation Summary L                              This. modification to the liquid radwaste system 'provides additional h
flexibility. in storage.and processing for long-term plant operation.
Modifications were ' performed per Regulatory Guide 1.143 criteria as -
required by PG&E's design . criteria.
J                              ~1 3)WI
: 5.        Reolace Reactor Coolant Resistance Temperature Detectors'(RTDs)'
LF                            DCP#.J-31961;Rev. 0 (Unit 1)
                            .This change' replaced the reactor coolant RTDs because their environmental qualificatica expired at the end of 1986. The replacement RTDs are;qualliied to. function within the expected radiation field, for
                              <40 years.
                            . Safety Evaluation Summary The' replacement RTDs' comply with specifications of the original RTDs and are qualified for-40 years. The temperature range, response time, and accuracy of'the replacement RTDs are equal to or better than those of      i the original RTDs.
: 6.        Reolace Solenoid' Valves of Main Steam Isolation Valves DCP# J-35761      !
Rev. 1 and J-36761 Rev. 1 (Units 1 and 2)
This design change replaced the solenoid valves of the main steam isolation valves with valves rated at higher temperatures.
                          ' Safety Evaluation Sum _ny The replacement' solenoid valves are capable of withstanding more severe postaccident-temperatures than the original valves. The replacement
        " .                . valves are Instrument Class IA requiring IEEE 323-1974 Class IE qualification. Other characteristics, such as physical size, shape, and performance, are unchanged..
: 7.        Reolace Steam Generator Feedwater Rina J-Tubes DCP# M-35476 Rev. 0 (Unit 1)
This change replaced the original carbon steel steam generator feedwater      i ring J-tubes with Inconel J-tubes. Inconel provides a suitable              !
combination of resistance to corrosion and to stress-corrosion cracking.    !
1 i
                    '1667S/0052K                                                - -          _      - _ _
 
7.
              ' ;a                                                                                ,
        ..    +    .
                                                                                                          ,j
                      . Safety'Evhluat h ammarv l
The'Inconel J-tubes increase the reliability of~the steam generators by-providing increased resistance to. erosion and corrosion of the.J-tube nozzles, thus enhancing.the; safety function of:the auxiliary feedwater
                                                              ~
system.-The new J-tubes'have the same s ometry as the original J-tubes
:and are compatible with the' service cormitions.
: 8.      Containment Interior Paint Inventorv DCP# M-28096 Rev. 4 M-28096 Rev. 4 . M-33052 Rev.- 4, and M-34052 Rev. 4 (Units 1 and 2)
This change has added to the-total containment interior. paint. inventory
                      'by the addition of a separate hoist for the missile shield and a new dome service crane.~--                                                            g Safety Evaluation Summarv During a LOCA, unqualified paint within containment is assumed to be              i'
                      ' removed..due'to the harsh environment, and to accumulate at the recirculation sump screen. PG&E Calculation M-591 has determined tho'
                      , amount of accumulated paint. required to prevent residual heat removal recirculation flow. The total amount of unqualified paint-(not conforming to PG&E Specification 8875) is well under the allowable                  i limits'and will not prevent post-LOCA recirculation flow.                        J
: 9.      Postaccident Monitorina System (RG 1.97) DCP# J-27357 Rev.=3, J-27311 Rev. 2 and 3-28311 Rev. 2t(Units 1 and 2)
This changa gives the revised temperature range for the newly installed
                      'postaccident monitoring instrumentation, which monitors the containment              i atmosphere. temperature and containment sump water temperature.
Safety Evaluation Summary The monitors provide control room indication of_ containment ~ atmosphere and sump temperature for operator information only. The specific instrutent temperature range envelops the temperature monitoring range given in Regulatory. Guide 1.97.
l-              10. Containment Water Level Indication DCP# J-35185 Rev.1 (Unit 1)                      .
This change provides additional containment wide range water level monitoring channels because the original monitoring channels were                  1 continuously out of tolerance (NCp# DC1-85-TI-N051).
Safety Evaluation Summary The newly installed instrumentation meets the same qualification (Class 18, Type A, Category 1) as the original instrumentation. The original system also remains in place as a backup to increase the overall reliability of the containment water level monitoring system.
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          . 11. Auxiliary Steam Pine Break' Isolation DCP# M-33716 Rev. O and M-34716
                ~Rev. 0 (Units 1 and 2)
This change added a new auxiliary steam isolation valve for each unit to isolate auxiliary steam supply to the auxiliary building in the event of an auxiliary steam line break in the auxiliary building. An existing auxiliary steam isolation valve (PCV-69), which would isolate auxiliary steam to both the auxiliary building and the turbine building, has been eliminated.
Safety Evaluation Summary 1
The new auxiliary steam isolation valve performs the same safety function as the original isolation valve (PCV-69), i.e., to protect safety-related equipment in the auxiliary building from an auxiliary    4 steam line break. However, auxiliary steam supply to the main condenser steam jet air ejectors, located in the turbine building, is not isolated by. closure of the newly installed isolation valve. Thus, plant availability is not affected by isolation of auxiliary steam to the auxiliary building. An auxiliary steam line break in the turbine building will not have an impact on safety-related equipment.
: 12. Reolace Three Control Room Area Doors DCP# A-35723 Rev.1 (Units 1 and 2)
This design change replaces three (3) inflatable seal doors with        ,
weather-strippeo (gasket) doors to the control room area.
SMgh Evaluation Summary Per PG&E design criteria, the new doors are designed to withstand seismic events and high energy line breaks, are fire rated and bulletproof, and will maintain air tightness. An air pressure test has  i been conducted for each replacement door. During installation, measures  j were taken to allow control room accessibility and maintain positive      i control room pressure.                                                    I
: 13. Modify and Reinstall Low Density Soent Fuel Ract_ DCP# M-35152 Rev. I and M-38360 Rev. 1 (Units 1 and 2)
The original low density racks were removed from the spent fuel pool, modified by the addition of bracing and added weld material, and reinstalled. In reinstalling the racks, the anchorage was changed from a bolted to welded anchorage at existing embedment plates in the floor of the pool.
Safety Evaluation Summary The fuel racks that are installed are the same fuel racks that were evaluated as part of the FSAR's original &:cident analysis. The            l modifications to the racks and rack anchorage vere shown, by 6nalysis, to meet the FSAR design criteria of the original racks, including design (DE), double design (DDE), and Hosgri earthquake loading conditions.
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: 14. Addition of New Soent Fuel Pool Coolina Pumo DCP# M-33785 Rev.'2 and                  i l'                              M-34785 Rev. 2 (Units 1 and 2)
This change added a'new, permanent 1y' installed spent fuel pool cooling
                                        . pump in parallel with the existing pump for each unit.
1 Safety Fvaluation Summary The new, permanently installed cooling pumps replaced the single, c    portable cooling pump that served as a backup, for both units, to the primary spent fuel cooling pumps. This provides immediate availability,            l in each. unit, of a' backup pump should'the primary pump fail.
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: 15. 'Soent Fuel Handlina Brackets DCP# C-35696 Rev. O, C-36696 Rev. O,                      '
C-37442 Rev. O, C-38442 Rev. O, M-33230 Rev. O. and M-34230 Rev. 1 (Units 1 and 2)
These design changes. involve the relocation and addition of brackets for supporting various tools in each spent fuel pool and transfer canal. The              'i tools: include the spent assembly handling tool, burnable poison rod _
assembly (BPRA) handling tool, rod control cluster (RCC) handling tool, and thimble plug. handling tool. In addition, light pole brackets and spare. anchor bolts were removed from embed plates in the walls and floor of the pools.
                                        . Safety Evaluation Summarv
                                        .The spare anchor bolts, light pole brackets, and tool brackets were removed and new tool brackets were added without affecting the pool integrity. The new. support brackets are designed-to meet the Hosgri earthquake load combinations. All work was performed prior to storing spent fuel in the pool.                                                              i
: 16. Steam Generator Blowdown System Modification DCP# M-35235 Rev. 0 (Unit 1)
This design change installed a piping system from the steam generator                  !
blowdown (SGBD) flash tank to the No. 3 feedwater heater in order to improve thermal efficiency by recovering heat from flashed steam within the blowdown flash tank.
Safety Evaluation Summarv 4
The SGBD system is not safety related. Appropriate steam flow controls
                                        .and instrumentation have been incorporated in the design to preclude any                !.
low-pressure (LP) turbine damage.
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: 17. Add Bearina Lift System for LP Turbine "C"    Rotor Bearina No. 8 DCP#.M-15286 Rev. 2 (Unit 1)                                                            i a                                                                                                                              1 The revised design of the spare LP turbine rotors required installation                l of a bearing lift system for the No. 8 bearing. It cons'..,ts of a locally            {
mounted pump with motor, filter, tubing, and instrumentation. A local                  i 3
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                  ; control console is mounted on the turbine pedestal, and electric tcircuits'in conduits connect to the existing turbine turning gear
                  ' controls.
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                  ~ Safety Evaluation Summary The bearing lift system: (1) is. powered from nonvital power supplies;.      I (2) does not interface with any Class 1E circuits;-(3) is not connected      !
with or immediately adjacent to any safety-related or safe shutdown        i systems; (4) is not associated with any accident mitigating functions;      J (5),is not covered by any DCPP Technical Specifications; (6) does not        '
compromise any existing 10 CFR 50 Appendix R reviews; (7) contains no radioactive ~ materials; and (8) is Design Class II.-
q          19. Redundant CVCS Letdown Filter DCP# M-27132 Rev. 2 (Unit 1)
This change adds a parallel, redundant filter for reactor coolant letdown?to the volume control tank to allow removal of demineralized debris with one filter out of service.
SAfgty Evaluation-Summary To maintain piping integrity, the new piping and supports are designed and constructed to equivalent codes as the original filter. ALARA considerations are incorporated into the design. No net increase in radwaste system inputs is expected.
: 19. Reccat Main Condenser Water Boxes DCP# M-36329 Rev. O and M-36536 Rev. 0 (Unit 2)
The main condenser inlet and outlet water boxes were blast cleaned and coated with a modified epoxide coating to prevent or arrest erosion and corrosion of'the water boxes.
Safety Evaluation Summarv                                                ''
This coating and the components to which it is applied scrve no safety    i or safe shutdown functions. It has no accident mitigating function. The    i evaluation of turbine. building flooding due to main circulating water system failurt is not adversely affected by this change.
: 20. Fire Hater System - South Site DCP# M-33127 Rev. 4 (Units 1 and 2)
A new fire water supply system was installed to service the southern areas of the plant site. The main system components (pumps, tank, etc.)
are located away from the power block structures.
Safety Evaluation Summary Adequate features werc incorporated into the design in order to not
: compromise the main plant fire water system, to which this new system, is connected. The main function of the new system is to provide 1667S/0052K I
protection to non-safe-shutdown and non-safety-related structures, systems and components. No plant safety features are in proximity to this new system, nor is the existing plant flooding analysis adversely
    -affected by this change. There are no vital electric power circuits or components associated with this system.                                    ,
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: 21. Backuo Overcurrent Protection for Containment Electrical Penetrations DCP# E-3459 Rev. 1, E-3941 Rev. 1  E-5415 Rev. 2, E-7140 Rev. O, E-11016 Rev. O, E-11426 Rev. 0 (Unit 1)
Redundant, appropriately qualified, in-s3 ries overcurrent protection      l devices were installed on electrical circuits penetrating containment to  I ensure single electrical failure protection for the penetration's physical integrity._
l Safety Evaluation Summary This change was required by the NRC as documented in the October 18, 1978 NRC meeting minutes of an October 12, 1978 NRC-PG&E meeting and in SER Supplement 8, dated November 14, 1978. This change provides redundant overcurrent protection devices, which will ensure that physical integrity of containment electrical penetrations is not impared by a single passive failure concurrent with an electrical single active failure of the primary overcurrent protection device, 1667S/0052K                           
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                                                        ' ATTACHMENT 2                            ,
PROCEDURE CHANGES FOR ANNUAL' REPORT March 23, 1986 - March 22, 1987 A procedure is described in the FSAR Update if it meets the following criteria:-
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: 1. The FSAR Update text contains a commitment to perform a manual action or establish an administrative control or program.
: 2. The FSAR Update text contains a detailed description of the methodology used to perform an a. ivity with mention of:
: a. equipment used (as apr priate),
                                  -b.  -limits on the activit), and/or
: c. order of steps.
: 3. The activity described in the FSAR Update could significantly affect the safety of the plant.
An FSAR Update system description that includes an explanation of how plant personnel can interact with the system does not necessarily constitute a procedure.
                  -The PSRC has reviewed all plan't-specific administrative and technical procedure revisions and concluded that they do not present unrevievod safety l questions.or changes to the DCPP Technical Specifications. None of the revisions.resulted in changes to procedures as described in the FSAR.
                ' Only one non-plant specific procedure change resulted in a deviation from
                'the FSAR Update. Charter NPG 5.1 was revised to change titles of members of.the President's Nuclear Advisory Comittee (PNAC). This change is strictly administrative and consequently has no adverse impacts on plant safety. Note that-this procedure is not subject to'PSRC review due to its applicability to General Office activities.
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