View source for RBG-20-994, Forwards Addl Info Requested in a Schwencer to Wj Cahill Re Revs to FSAR Subsections.Revised FSAR Pages Supporting Revs Encl.Revs Will Be Included in Future FSAR Amend

{{Adams
| number = ML20128E850
| issue date = 05/15/1985
| title = Forwards Addl Info Requested in a Schwencer to Wj Cahill Re Revs to FSAR Subsections.Revised FSAR Pages Supporting Revs Encl.Revs Will Be Included in Future FSAR Amend
| author name = Booker J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = Denton H
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000458
| license number = 
| contact person = 
| document report number = RBG-20-994, NUDOCS 8505290489
| title reference date = 04-30-1985
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 38
}}

=Text=
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GULF STATES                  UTILITIES COMPANY P O S T O F FIC E D O X 2951 =DEAUMONT. TEXAS 77704 AREA CODE 713 838 6631 May 15, 1985 RBG 20,994 File No. G9.5 G9.8.6.2 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

==Dear.Mr. Denton:==

River Bend Station - Unit 1 Docket No. 50-458 Enclosed are. the Gulf States Utilities Company (GSU) responses to the letters from Mr. A. Schwencer (Nuclear Regulatory Commission - NRC) to Mr. William J. Cahill (GSU) dated April 1 and April 30, 1985.
Attachment 1 provides a summary response to each request for additional information (RAI) attached to the referenced letters, while Enclosures 1 through 3 provide revised Final Safety Analysis Report (FSAR) pages supporting statements in Attachment.1. Those FSAR revisions contained in Enclosures 1 through 3 will be included in a future FSAR Amendment.
Sincerely, f . E. M J.E. Booker Manager-Engineering Nuclear Fuels & Licensing.
;                                                      River Bend Nuclear Group
                )N, JEB/WJR/JWL/j e L
Attachment (1)
Enclosures (3)
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ATTACHMENT 1
: 1. Question 640.1, Item (3): The response to this question should be modifie'd to address revised FSAR subsection 14.2.12.1.26 (Normal and Standby Service Water Systems Preoperational Test).

===Response===
See revised Q&R page 1.8-3 tontained in Enclosure 1.
: 2. Question 640.6: Test abstracts, as noted, should be modified as follows:
: a. FSAR    subsection     14.2.12.1.4   (Nuclear   Boiler     System Preoperational     Test) should provide appropriate acceptance criteria as specified in this item. It is not appropriate to reference    the    preoperational test description itself for acceptance criteria as this method does not clearly indicate the source of the acceptance criteria to be used in determining that adequacy.

===Response===
The acceptance criteria for items 4.a and 4.b, "within limits of the test specification," refer to the General Electric Company's (GE)
Preoperational Test Specification specific to RBS (Document No.
22A5296AG.) FSAR subsection 14.2.12.1.4.4 is revised accordingly in Enclosure 3.
: 3. Questions 640.21 and 640.29: The response to these questions are in part    or completely addressed by FSAR subsection 14.2.12.1.70 (Safety-Related Ventilation Systems       Environmental   Design- and Technical Requirement Preoperational Test) and should be modified accordingly.

===Response===
See revised Q&R pages 14.2-27 and 14.2-35 contained in Enclosure 3.
: 4. Questions 640.25: The exception taken to Regulatory Guide 1.68, Initial Test Programs for Water-Cooled- Nuclear Power Plants, as contained in FSAP. Table 1.8-1, " Regulatory Guide 1.68, Rev. 2 (August, 1978)," Section 11.2 should be modified to state that emergency loads are tested at reduced voltage in FSAR subsection 14.2.12.1.44.

===Response===
See revised Table 1.8-1, Page 96 of 193 contained in Enclosure 1.
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: 5. Item 14A:     FSAR Figure 14.2-6, " Maximum Acceptance Drive Flow Following Pump Trip," should be provided or .FSAR subsection 14.2.12.3.27.2 .(Recirculation. System    -
Trip of Two Pumps) should reference an appropriate document.

===Response===
See revised page 14.2-177 contained in Enclosure 3.
       -6. Item 14B: FSAR subsection 14.2.7 (Conformance of Test Programs with Regulatory Guides) should reinstate Regulatory Guide 1.52 (Amendment 15 modification).

===Response===
See revised page 14.2-18 contained in Enclosure 3.
: 7. Item 14C: FSAR subsection 14.2.12.1.36 (Stsndby Diesel Generator Preoperational Test) and FSAR Table 1.8-1 (Conformance to NRC Regulatory Guides) should be modified to reinstate testing in conformance with Regulatory Guide 1.108, Positions C.2.a(3) and C.2.a(9), or FSAR Table 1.8-1 should be modified to provide additional technical justification for any exceptions to this guide.
The statement contained in FSAR Table      1.8-1   and FSAR subsection 8.3.1.1.5.2 does not justify the exception.

===Response===
As indicated in FSAR Section        8.3.1.1.5.2, th'e standby diesel generators were run for 24 hours at their rated load of 3500 KW.
However, the actual diesel loading will not be above 3130 KW (see Figures 8.3-2a and 2b).       The 3500 KW, 24- hour run therefore represents   a' loading greater than 110% of the qualified load (3130 KW) and thus meets the intent of Regulatory Guide 1.108 Position C.2.a(3). This    discussion   is reflected in revised Section
           -8.3.1.1.5.2 as shown in Enclosure 2 and the' position clarification statement for Regulatory Guide. 1.108 is modified as shown in Enclosure 1. In addition, the RBS HPCS Diesel Generator was subjected to a 24 hour run at its continuous rating of 2600 KW, 2 hours of which it was subjected to a 110 percent overload test.
;           This is reflected in the revised section 8.3.1.1.5.3 contained in-
!           Enclosure 2. Finally, no modified starts .w ill be used to meet
           ~ Regulatory   Guide    1.108   Position   C.2.a(9).      Therefore, the clarification statement in Table 1.8-1, as well as other FSAR references to modified starts, have been deleted as shown in Enclosures 1, 2 and 3.
c.
1
: 8. Item 14D: FSAR subsection         14.2.12.3.22.2   (Main Steam Isolation Valves    -
Full Reactor Isolation) should provide or reference acceptance criteria regarding increase in heat flux and done pressure.
Response:                                                                ,
See revised page 14.2-164a incorporated in FSAR Amendment 17 and contained in Enclosure 3.
: 9. Item 14E:       Either reinstate,-     change,    or  provide  technical justification for the following in FSAR Figure 14.2-5, "Startup Test Program:
: a. Test No. 13 " Process  Computer" Test at TC6 (Regulatory Guide 1.68, App..A.5.r).
: b. Test No. 26 " Relief Valves" Test at TC6 and Note 24 (Low-Low Set Logic Function Test).
: c. Test No. 27 " Turbine Trip and Generator Load Rejection" - Note 19 should be modified to state that a generator load rejection will be conducted at 100% power in accord with revised FSAR subsection 14.2.12.3.24, " Turbine Trip and Generator Load Rej ection."

===Response===
: a. TC6 has been reinstated for Test No.        13, see revised Figure 14.2-5 contained in Enclosure 3.
: b. . Test numbers 25b (Full Reactor Isolation) and 27 (Turbine Trip-and Generator Load Rejection) will be performed at TC6 to verify the SRV low-low set logic function rather than Test No. 26 (Relief Valves). This is reflected in revised Figure 14.2-5 and on FSAR pages 14.2-164a, and 166 through 169 contained in Enclosure 3.
: c. Note 19 to Figure 14.2-5 has been revised to state that a Generator Load Reject will be conducted at TC6, see Enclosure 3.
I.-
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u-                 ._ 2                                                 ,
f Enclosure 1 This Enclosure provides revisions to the position statements for Regulatory Guides 1.68 and 1.108 contained in Table 1.8-1, and revises the response to Question 640.1. As such, this enclosure provides the necessary FSAR changes to address items 1 and 4, in full, and item 7, in part, of Attachment 1.
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r --                                                         u                            e Rwturaq' Guzs I.68 RBS FSAR TABLE 1.8-1 (Cont)
: 18. Appendix A, paragraph 5.d.d (p. 1.68-18)
Regulatory    Guide 1.68.2      is  addressed   in   a separate compliance statement.
: 19. Appendix A, paragraph 5.o.o (p. 1.68-18)
Vibration   on NSSS    piping in the drywell is monitored   and evaluated using remote sensing devices.
: 20. Appendix C,  paragraph 1.a.  (3)(d) (p.1.68-20)
Regulatory Guide 1.37 is addressed in a separate compliance statement.
II. Exceptions
: 1.      Paragraph C.2 (p. 1.68-4)
Surveillance    tests    necessary to denonstrate proper operation of interlocks, set points,        and other protective features, systems, and equipment required by the technical specifications are perforned during the. initial test program. This does not include the performance of            formal surveillance tests required by 10CFR50.36.         The actual performance of these tests is not within the scope of the initial test program.        Chapter 16 of this FSAR defines the formal surveillance test requirements.                                      s
: 2. Appendix A,   paragraph 1.q(2) (p. 1.68-8)
Emergency loads are tested at normal voltage.
l                           Operation at other than rated voltage may be               is considered     as     destructive    testing. / The
          /NbbNU            preoperational tests      demonstrate    the    proper functioning    of the diesel generator        voltage regulator under an       auto-start    and    loading condition.
: 3. Appendix A, paragraph 1.h(1)(a) (p. 1.68-9)             l5 Expansion tests are not performed during the preoperational testing of ECCS.         RCIC turbine steam    supply and exhaust lines are visually Amendment 16                96 of 193              February 1985 l
                                                                                          ..--.J

1 I
Insert for Table 1.8-1, Page 96 of 193 However, the ECCS Integrated Initiation during Loss of Offsite Power (LOOP) Preoperational Test, Section 14.2.12.1.44 describes a test for the DC system loac'.s (during a LOCA coincident with a LOOP and inoperable battery chargers) to verify the voltage levels remain greater than_ or _
equal the minimum design values and load profiles are within their design values a
4
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%uurtwy Giul;s MQ3 RBS FSAR                                                    i I
l TABLE 1.8-1 (Cont)
    /AS9e7 Y      -
Paragraph      C.2.a(3)      -
For  the g tandby diesel           #5 generators,4ene:pti;n in tak;n te performance of M T /S              the overload test (:in::             tr.: di; :1 ;;n: :ter:9     M #1 D W MN                 eill net he Oper t:d b:ce theii i.t.d iv.J.5                    AO Dot v
The onsite preoperational 8.3.l. i.C.2' f g.       Paragraph C.2.a(9) -                                             38 reliability tests required by this section were performed / ::.tr. tr.:     :n;;pti:n   tr.;t tr.: :t;ncyl di ::'. ;:n::::::: .:::: cubj::::d t: 'tr: f;; t ct:rt: :nd t;n         T.:difi d ;t;;t;/as described iI[
J S::tienA8 .3.1.1.5.2.
_.s    Secnons Paragraph 8.3.1.1.s C.3.b
: 2. / Aub Regulatory    Guide 1.16   is 67                                    -
addressed in a separate compliance statement.
FSAR Sections - 8.3.1, 14.2.12 Amendment 16                  146a of 193                   February 1985 y

Insert for Page 146a of 193
: 3. Paragraph C.2.a   - Periodic testing will be as required by Technical Specifications.
__U

4 RBS FSAR QUESTION 640.1 (1.8) ( 14.2. 7 )
Regulatory Guide 1.68 - Rev. 2 (Table 1.8-1).
Address the following:
: 1.          Modify your. exceptions to Appendix A, Positions 1.c and 5.g.g, to provide a commitment                                        to               include   in your. test program any design features to prevent or mitigate    anticipated transients                                       without.                scram (ATWS)    that may in the future be incorporated into your plant design.
: 2.          The staff recognizes that there is currently no Loose Parts Monitoring System. at the River Bend Station.              Commit to the test requirements of Appendix A,                     Positions 1.j(6) and 5.n,                                    for such systems that may be installed in the future.
: 3.          Verify that sources of water used for long-term core cooling are tested to demonstrate adequate NPSH and the                       absence of vortexing over range of basin level from maximum to the minimum calculated 30 days        following                          LOCA. (Clarification                               of Appendix A, Position 1.h(10).)

===RESPONSE===
: 1.          The exceptions to Regulatory Guide 1.68 Appendix A, Positions 1.c and 5.g.g have been deleted.
: 2.          A   loose parts monitoring system (LPMS) is provided in the River Bend Station design.                                                         See revised     it Section 4.4.6.1, Tables 1.8-1 and 14.2.12.1.69.
!                  3.          Section 9.2.5.2 describes the ultimate heat sink j                              and its design to provide sufficient NPSH and vortex-free operation.% IThereferr,                                                   ne t : tin; ir' Y
                      \ n-. .=: t= : === t: t= t.'.=== ==Lt==L=.
5ecrai fil.2. Q. /. % TESCRIB6S TH6 Pea $se-AYIMAL M 5 Cr&CliSD TO MBAJf*V' Vb2TE)(-
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Amendment 11                                        Q&R 1.8-3                                             January 1984

Enclosure 2 This enclosure provides revisions to various pages and sections of FSAR Chapter 8.3 to support revisions to the position statements- for Regulatory Guide 1.108 (See Enclosure 1) and to address item 7, in part, of Attachment 1.
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: 8. 3 .I. I. 4 . l (
SrADZ;il % QuAuricArlon 7garig, RBS FSAR to    the    equipment      that      each     switch      controls (Section 7.1.2.3).
Factory   testing of the standby ac power systems was performed as defined in IEEE-387,          Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations.
Standbydieselgenerator[1EGS*EGlAf2           1EC9+EC19 '?er #given      is
     $7AET 37!typ # qualification tests W in accordance with IEEE 387 and IEEE 323/
Bend Station in[alificationtestswereperformedatRiver accordance with Regulatory            Guide 1.9, Paragraphs C.13 and C.14,        and Regulatory Guide 1.108, as discussed in Section W 8.3. /. /. f.b ,
nr nie TDI VAcrchy. EACH STR R T VE2 6 XA'000 ~E ST                (DAS penwwmED                                                                 #
1%:vn A crAUDB/ 787DPSRGruB6 W 150 t 10 APD     MD         pckup ct- 19so kW LOITHin lo EScoubS CV THE STARY St&UAL (THOGG LC6ec @ gyner pAtut2GB.)                       .
t'petouS AbbtTIOCAL ~Ibl MCzb@ QuAupicarton T&w 1062G FGBfoemeb het ROTH STAMZ;%V Z>lC56L G60-eeAroes As Discusseb in frern a a- & c e nce 3.
Ia ADD'MO ,
Amendment 16            8.3-30a                      February 1985 9
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  . 6L 3.1. t . #.a. I HKS 1s aaAURCAruJ %Sn%
RBS FSAR
: 1. Prior to initial fuel loading of the reactor unit, a series of tests will be conducted to establish the capability of the HPCS diesel generator unit to consistently start and                                  load within                       the        required time.
: 2. With the exception of those diesel engine / generator designs that are identical (minor changes may be justified by analysis) to the diesel generator unit (s) which have been previously qualified for the HPCS application,                                        all other different diesel engine / generator combinations will be individually qualified for reliable start and load acceptance requirements.
49/g       3. An          accentable start and load reliability test is defined as follows: A total off497 valid start                                                                   and UOM         loading tests with no failure orp4G valid start and                                Y M W1964           loading tests with a single failure will                                                                          be     N OC IVESGU3,1) performed.                              Failure of the                         unit       to     successfully complete this series of tests as prescribed will require a review of the system design adequacy, the cause of the failure to be corrected, and the tests jpg     continued until/4Gr9alid tests are achieved without exceeding the one failure.                                               The start and                         load tests will be conducted a: f:11:U:"" see 67 co@ M97(;nedrS,                                                                 p 16                                                                                                                                                f A
_- _-_+_._-*--+-
n_ n_ , A   c, J L.               O het fast a t e.- t s
                                        ?       2.         El m dified : tart:
l                              The fast starts'are conducted fre- th-                                                       ~*4"        "^"***?'
                            . r::               by cinul:ti:n f :n ESF ci;n 1 with the engine
!                              in          a ready standby status,                                            F:11:uin; :ch fred"
: tart, th: :ngin: 1: leaded te                                                the       EEF        hur       -l e nd '~
                                                                                                                         +w,+        3-,a_cm.
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                                                                                                                          ... -         - -     -..m-A w.          mum            cai cieg r+., rte Anclude                         a ggy g          7 pp .,,, $ _ e , 7 rece- ended by the 2nuf2         turer, op ypg         .prelube                      peried 2 loading tof;pproni-.;tcly 2f 00 kS' within                                                          to 5 min,"
empf and operation at this load forf ;;reninnt:11'1 hr.
4tRD           M odified etart -ry be perferred '-?ith the en;ir- at                                                                       #MD jit: eper2 ting t perature.                                               During and/or following this testing, some individual components of the l
j                              diesel generator or its support systems may require
!                              maintenance and/or replacement.                                                  This maintenance and/or                 replacement                 due            to     wear      does not require retesting.
Amendment 16                                           8.3-33a                                        February 1985
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RBS FSAR                                                              1 l
l The capability for testing and calibrating all actuation                                                    l 1
devices, circuits, electrical protective relays, and related instrumentation during normal operation is designed into the power systems important to safety and in accordance with the                                               i recommendations             of  Regulatory Guide 1.22.                            Provisions to perform       nondestructive           tests                          under   simulated      fault conditions are              provided. This                includes        but  is  not   limited to the ability of the protection system to initiate the -
operation of the actuated equipment.
8.3.1.1.5.2       Standby Electrical Power Supply Systems Maintenance and testing of the standby diesel generators are                                         -
conducted to ensure that all egmporents and auxiliaries are operational within their design limits.
In addition to the qualification tests conducted on each diesel generator set at the engine manufacturer's factory, ME TS       tn ::      tanety eic; i            generater :::: wer: cue.;eetce :: twe
      /p )d>   -fast : tarts and ten m;dified starts after their inctallation
                                         ^                                                           start "hi4h et th: cite.                . modified tart in defined 2:
b           include: ; prelube . cried                :             reccrc:nded by th                   engiee g mfN 18
               = nuf :turer,         1 :eing t: 7s percent-of-th: :xi.um-d iw lead w thin 0 to 5 min,              and ;parati:n at this--40 d fee
   /[6S3ISI[   spprcrimately 1 hr.                The mcdified starte may-be perferr:3 with the engine at it: Operatin; t: per:ture.                                            The feet j{
start: cr: 00nducted fr:r the m:in : ntrol : r in : rc:dy                                              (i) str.;dby statu:.            During :::h fact : tart th:                               :gine:   ard 10:d:d t        th: ESF hu 10:d ch:Un in T2hl: 9.3-2 2nd run it th t lend for ppr:nir:tely 4 hr.
             ' Each    diesel     generator set was given a load capability test at their rated load of 3,500 kW for 24 hr. / Th: :n;in:: .:: r: 3#          ~
F       net   ::t:d at their 2 hr r: ting cin : th::c ::t: vill n:t he A>
  /MSE @       m' - - -e 3heve the r2 tee leze p
      ;2.
The following tests were performed in accordance with IEEE-387 after complete installation of the standby diesel generator system at River Bend Station.
: a. Starting test
: b. Load acceptance test 1
: c. Rated load tests Amendment 16                           8.3-36                                      February 1985

Insert i for Page 8.3-36 the Standby,. Diesel Generators are subjected to 69/n (where n is the number of diesels, 2) start and load tests with no single failure or 128/n- start and load tests with a single failure. Failure of a diesel to complete this series of tests will require a review of system design adequacy, the cause of-failure to be corrected, and the tests continued until 128/n valid tests are achieved without exceeding the one failure criterion. The start-and load tests are conducted with the engine in a ready standby status and include a loading to at least 50% of the continuous load and operation at this. load for at least I hour.
Insert 2 for Page 8.3-36 However,' as indicated in Tables 8.3-2a and 2b, the standby diesel generators will not be loaded above 3130 KW. Therefore, the 24-hour, 3500 KW load capability test more than satisfies the 1i0% overload-requirement of paragraph C.2.a(3) of Regulatory Guide 1.108 when applied to the qualified load of 3130 KW.

RBS FSAR surveillance or system            operating procedure to place the diesel in an automatic standby readiness condition.
Compliance with Technical Specifications, administrative and system operating procedures, and the preventive maintenance and surveillance testing schedule ensures optimum equipment readiness and availability upon demand.
8.3.1.1.5.3    High Pressure Core Spray Power Supply System
               ' Readiness    of the HPCS diesel generator is demonstrated by 12 , periodic testing according to Regulatory Guide 1.108 and is described in the Technical Specifications.                         The testing program is designed to test the ability to start and accept 2Mdj3767       the HPCS diecel generator             design          loads connected to bus 1E22*S004. N er the HPCS di ::1 ;: :::ter h:: re hed -its                     '
gg     is l ongine     t:=perature equilibrium,             it i      run undcr its rated Kl@904C ET L12:e f:r 2 hr nd th::. run for 22 hr unear the rate                        10&3.
(dy7//       Thir,   ensures     that cooling    and   lubrication       are  adequate for extended periods of operation. Full functional tests of the
  /              automatic control circuitry are conducted on a periodic basis to demonstrate correct operation (Section 7.3.2).
Means are provided for periodically testing the chain of system elements from sensing                devices         through    driven equipment     to      assure     that the HPCS power supply is                       j functioning.in accordance with design requirements.                       The drawout feature of protective relays allows replacement relays to be installed while the relay that is removed is bench tested and calibrated.
is        Startup of onsite power units can be initiated by simulation of LOCA signal or loss of power to the plant auxiliary power system. Connection of the HPCS diesel generator to the HPCS bus takes place automatically on loss of plant auxiliary power to the HPCS bus (HPCS bus low voltage). The HPCS diesel generator bus            directional            overcurrent,    ground overcurrent,        and phase overcurrent protective relaying provides a trip to the offsite power feeder breaker in case of loss of offsite power while the diesel generator is in the test mode operation.
e s
l Amendr.ent 16                     8.3-38                       February 1985 i
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                                  ,,           -        .-    ,   -. -              f-

Insert for Page 8.3-38 The HPCS Diesel Generator is run for 24 hours at its continuous rating of 2600 KW, two hours of which it is subjected to a 110 percent overload
                             . test-(see Table 8.3-3).
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5;Sp2wr4X 1:GSCU1176 eta AW                 Sn@02>APJ>S RBS FSAR Regulatory Guide-1.9
          'In   accordance .with Regulatory Guide 1.9, the ratingscon-     of standy diesel generators LEGS *EGlA and LEGS *EGlB        are tinuous load rating of 3,500 kW each, and a 2-hour rating of 3,850.kW each, which exceeds the sum of the loads required.
The sequencing of large loads at predetermined intervals (Table 8.3-2) ensures that large motors will have reached rated speed and that voltage and frequency will have stabilized before the succeeding loads are applied. The de-crease in_ frequency- and voltage has been. verified to be within-95 and 80 percent of nominal, respectively.                 l2s Recovery of voltage and frequency to within 10 percent and 2 percent of nominal, respectively, has been verified to be accomplished within 40 percent of the sequencing interval of
          'S sec. _ Step loading and disconnection of the total diesel generator     nameplate-rating load does not cause the standby diesel generator to exceed 110 percent of normal speed, thus precluding an inadvertent overspeed trip.
The reliability of the standby diesel generators has been substantiated by an extensive test program.              The tests verify the following diesel functions:
: 1.   . Diesel fast start Ord redifi:d :t:rt* capabilities      l1 s
: 2. Load carrying capabilities
: 3. Load shedding capabilities
: 4. Ability of' the system to accept and carry the ap-plied loads up to its rated capacity
: 5. Long-term  no load running of       the   diesel  unit without any detrimental effects.
[
The reliability of the system to start and accept loads in a prescribed time interval has been demonstrated by . prototype qualification test data augumented by analysis to verify the ability of the River Bend Station standby diesel generators to perform their intended function, and has been further verified by preoperational tests. The preoperational tests
          . described     in Section 8.3.1.1.5.2 verify reliability af-         ts ter plant installation. Full-load tests have          been   per-formed     during  preoperational  testing at   the   River  Bend Station on each diesel        generator  set    to    demonstrate the start and load       capability of the. units within the        h8 Amendment 16                  8.3-49                February 1985

8.9.l.9.9.Q-gg w guppy sys7em -Zw.E M @ C 2/ M //g g g y                         BS FSAR Regulatory Guide 1.9, Position 1 Conformance Table 8.3-3 shows that the continuous rating of the diesel generator is greater than the maximum coincidental steady-state loads requiring power at any time.              Intermittent loads such as motor-operated valves are not considered for long-term loads.
Regulatory Guide 1.9, Position 2 Conformance See Table 8.3-3 for the 2,000-hr rating of the HPCS diesel generator, the 30-min rating, and the maximum coincidental load for conformance with this position. The ratings are described in Table 8.3-3. The long-term steady-state load shown therein is within the continuous rating of the diesel generator.
Regulatory Guide 1.9, Position 3 Conformance M              J The load requirements     4 xill b:fverified. Mn_iu67//v t :t det: .ill 5: 5" fincluded in thic CA:' fcilcuin;; th; preoperational testsj 2EstW&b M) p5AB Sirc7kws /Y.2 9./.8 t%2> M. 2. /2. /.hkl.
Regulatory Guide 1.9, Position 4 Conformance The design function of the HPCS diesel generator unit is considered to be a justifiable departure from                      strict conformance to Regulatory Guide 1.9,               regarding  voltage and The
[i frequency limits during the initial loading transient.
HPCS    diesel generator       loads consist of one large pump and I'
motor combination (approximately 2,500 hp), one medium size pump (450 hp), and other miscellaneous loads; consequently, limiting the momentary voltage drop to 25 percent and the momentary     frequency      drop      to      5    percent    would not significantly enhance the reliability of HPCS operation. To meet these regulatory guide requirements, a diesel generator unit approximately two to three times as large as that 15  l required    to carry the continuous full load would be necessary. However, the          frequency and voltage overshoot requirements of Regulatory Guide 1.9 are met. A factory testing program       on a prototype unit has               verified the following functions:
: 1. System fast-start capabilities
: 2. Load carrying capability
: 3. Load rejection capability
: 4. Ability of the         system     to    accept   and carry the required loads Amendment 16                  8.3-56                        February 1985

RBS FSAR Reference - 8.3 Subramanian,    C.V.,     Seismic  22
: 1. Henrie,      D.K. and Qualification Review Team (SQRT), Technical Approach for Re-Evaluation of Equipment, NEDE-24788-2, December 1982.
: 2. Letter from J. E. Booker, Gulf States Utilities Company, Beaumont,     Texas,   to    H. R. Denton,      U.S. Nuclear     is Regulatory         Commission,         Washington,         DC, February 10, 1984.
3 , W i Fe o v) 4.G..h h CTArss @tuTies 3
Comram, Bentunoar, Texas , To u.R. bearg R.S. MufGAR MyopJ/ MmlSaosJ ,
ODasulmErro3,D.c., Q u y,lqsg                       (gsu
         /ense G. Esc- posgu).
Amendment 13                   8.3-87                    June 1984

Enclosure 3 This Enclosure provides revisions to various pages, tables and sections of FSAR Chapter 14.2 to address items 2, 3, 5, 6, 7 (in part), 8 and 9 of Attachment 1.
d I

RBS FSAR power       plateau   are    reviewed evaluated, and approved by the     7 augmented FRC before proceeding to the next test plateau.
14.2.6      Test Records A    single copy of each test procedure is designated as the official field copy to be used for test documentation.              The official      field   copy   of each  test  procedure  and information specifically called for in the procedure, such as completed data       sheets,    tables,      logs,    chart recordings, etc.,
constitutes the         completed     test     procedure. Completed preoperational       and   initial  startup  test  procedures  are made a part of the permanent plant file and are retained for the life of the plant.
14.2.7     Conformance of Test Program with Regulatory Guides The following matrix lists regulatory guides used in the development of the Initial Test Program and the phase (s) of the program (as described in Section 14.2.1) to which they apply. The program complies with the intent of these and other      regulatory guides following the interpretations, clarifications, and/or exceptions discussed in Section 1.8.
Test Phases Reg.                                                      Initial Guide            Preliminary         Preoperational         Startup 1.8                  x                    x                     x 1.20                                      x                     x 1.30                 x                    x                     x 1.33                                      (25                   x
/meer   1:n
           . 58                 82' is   1.68                                      x                     x 1.68.1                                    x                     x 1.68.2                                    x                     x 1.80                                      x                     x 1.108                                     x 1.140                 x                   x                     x
          '1'    For syt.tems in the Preoperational Test Phase, only Sec-tions 5.2.19 and 5.3.10 of ANSI N18.7-1976 are applic-able.
82'    SWEC personnel directly involved in Preliminary Test Phase testing activities are qualified in accordance with Regulatory Guide 1.58, Rev. I with exceptions as Amendment 15                     14.2-18                 November 1984

i~
Reg..                                           Test Phases Guide                 Preliminary            . Preoperational                    Initial Startup Insert for Page 14.2-18 1.52                        x                                x                        x 1
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RBS FSAR Is
: 4. Acceptance Criteria
: a. Nuclear boiler      process instrumentation set points are within                                    the 4 test limits       of specification,                                         g             g
: b. Isolation valve operating times                      are within
,                         limits of the test specification.
is
: c. Capacity    of     the   MSIV       accumulators              is sufficient to operate the MSIVs the required number of times.
:                    d. Operability    of the main steam drain valves is verified.
14.2.12.1.5    Residual Heat Removal System Preoperational Test
: 1. Test Objectives
.                    To  verify that     the   residual      heat removal (RHR) system provides     the operational functions:
following       safeguards              and       [
: a. Low pressure coolant injection (LPCI)
: b. Suppression pool cooling
: c. Shutdown cooling
;         Amendment 13                   1$.2-30                                June 1984

RBS FSAR
                                 -load    in   which   overspeed   limits   are  not exceeded.
: g.          Demonstrate full-load carrying capability of the diesel. generators for a period of not less is l                        than 24 hr at 3,500 kW.       Verify that voltage and frequency are maintained within           test limits and that the diesel cooling systems function within test limits.
: h.          Demonstrate functional capability at operating temperature conditions by reperforming tests d and e above immediately (within 5 min), after completion of the 24-hr load test g above.
: i.          Demonstrate the ability to:
(1)   Synchronize the diesel generators with offsite power while connected to the standby load (2)  Transfer    the     load   from the    diesel generators to the offsite power (3)   Isolate the diesel generators and restore them to standby status.                       [
: j.         Demon strate   that the rate of fuel consumption while operating at the DBA load is .such that the requirements for 7-day storage inventory are met for each diesel generator.
: k.         The reliability of each diesel generator unit is demonstrated as per' the RBS position on is is                          Regulatory Guide 1.109. paragraph C.2.a(9), as stated in Section    . .
8.3. h /,5.o1
: 1.         Demonstrate that the clipability of the diesel generators to supply standby power within the required time is not impaired during periodic
;                                 surveillance' testing.
: m.         Demonstration of reliability and independence of the redundant diesel generator units is l
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Amendment 16                             14.2-84                February 1985 L
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M.2.12. 3. 2Q c2                                                                          '
Tssr Akuttue2 XB RBS ESAP.
flux does not exceed the Level 2 criteria by more than 2 percent of rated value, s
Feedwater control system settings prevent flooding of the steam lines.
lAM$                =
Level 2 The RCIC system adequately takes over water level protection. The relief valves reclose properly (without leakage) following the pre.ssure transient.
For    the    full   MSIV closure from full power, predicted analytical results based on beginning of cycle design-basis analysis, assuming no equipment failures and       applying     appropriate     parametric corrections,    are used as the basis to which the actual transient is compared. The following table specifies the upper limits of these criteria during the first 30 seconds following initiation of the                              '
indicated conditions.
Initial Conditions               Criteria Dome             Increase In     Increase In         1:
Power    Pressure       Heat Flux       Dome Pressure
(%)       (psia)           (%)               (psi) ''
100      1040               <4 NBR            <132.7            17 Initial action of the RCIC and HPCS is automatic when water Level 2         is    reached,     and     system performance is within specifications.
Recirculation runback occurs. Recirculation pump trip is initiated when Level 2 is reached.
lW S                  7 14.2.12.3.22.3   Test Number 25C - Main Steam Line Flow Venturi Calibration
: 1. Test Objective                                                        ,
y The purpose of this test is to calibrate the main steam flow venturis at selected power levels over the entire core flow range.        The final calibration takes place with the data accumulated along the 100 percent rod line.
Amendment 17                   14.2-164a                  March 1985 4

s-Insert 1-for Page 14.2-164a
                     -The low-low set pressure relief logic functions to preclude subsequent simultaneous SRV actuations following the initial SRV actuation due to g  original pressurization transient.
    ,s-
             -        Insert 2 for Page 14.2-164a y
When the low-low pressure relief logic functions, the open/close actions of the SRVs occur within 113 psi and 20 psi, respectively, of their
                     ' design points.
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1 W.a.c. s. c23
: Test Lwntice 96                                      RBS FSAR flow is       sonic.      This is true if the back pressure is less than 55 percent of inlet pressure. The GE design specification required the back pressure to                         ,
be less than 40 percent of the inlet pressure,                    and      '
present designs have back pressures on the order of 30 percent of the inlet pressures.                    Methods of calculating line losses             and  pressure           drops are reliable enough to assure that            the   15     percent. to 25 percent conservatism in the                design        more than offsets       any     slight       inaccuracies              in   the calculations.         A major blockage of the line would not necessarily be offset and it                       should      be-determined        that      none exists through the BPV response signatures.
Vendor bench test data of the SRV opening responses are available onsite for comparison with design specifications.
During operation transients,              such as MSIV full closures        and    turbine       trips / generator           load rejection,        the operation of the safety grade low-low pressure relief logic system is monitored.
A comparison between the reactor pressure behavior and SRV actuations are made to confirm open/close set points and containment load mitigation through the prevention of subsequent simultaneous                         SRV  {
actuations.          Recirculation      drive        flow,       loop s
vibration, and pump head are recorded for one pump as a noncavitation check during low-low SRV action.
: 4. Acceptance Criteria Level 1
(                                   a.       There    is      positive    indication             of steam discharge during the manual actuation of each valve.
L.       The    1;W-les       ;;t   p;;;;;;;      ;;11;f 1;;i; functiene te preclud: rub::qu nt sinultan cu:
l                                            SRV    ::tuati:n       fell uing the initi:1 SRV l                                            ccturtien due t:          crigin:1     prc::uri::ti:n usanal6nt.
I l
Level 2
: a.      Pressure control system - related variables
_3 (RPV dome pressure, neutron monitoring) may i
contain oscillatory modes of response.                     In Amendment 5                      14.2-166                       August 1982 l
i l

    /C. /2. 31 a                                                                          l RBS FSAR l'E&                  these  cases,     the    decay    ratio    for   each j                  controlled mode       of   response is less than or 5
equal to 0.25.
4
: b. The temperature measured by thermocouples on the discharge side of the valves returns to within 10*F of the temperature recorded before               l the valve was opened.       If pressure sensors are
   -                         available, they return to their initial states               ;
upon valve closure.
  ;                    c. During the 250 psig functional test the steam flow through each relief valve, as measured by 4                          the initial and final bypass valve position,
  }                          is not less than,10 percent of valve position
(-                        under the average of all valve responses.
  !                    d. During the rated pressure test the steam flow through each relief valve, as measured by MWe, is not less than 0.5 percent of rated MWe less than the average of all the valve responses.
  ,_                   e.    " hen   the     leu-icu     pr:::ur: reli f 1:gic        '
functiene, th: p:n/cle : ::tien Of the SPNs l
cecur       within       112 pei     and     d20 pei, t     ggf                  respectively, Of their de:ign peints.                  i 14.2.12.3.24   Test Number 27 - Turbine Trip and Generator                s Load Rejection
: 1. Test objective The purpose of this test is to demonstrate the j                     response of the reactor and its control systems to protective trips in the turbine and generator.
: 2. Prerequisites t                      The appropriate preoperational tests have been
!.                      completed; the FRC has reviewed and approved the test procedures and initiation of testing.             All i~
controls    and    interlocks       are     checked     and instrumentation calibrated.
s r*
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Amendment 5                   14.2-167                   August 1982
  +5 1

iH.D.ta 3. .aq
. N 4.)(.J./7) M [ g                RBS ESAR
.                                              ~
: 3. Test Procedure                                                     <
 ,                Turbine trip (closure of the main turbine stop valves within approximately 0.1 sec) and generator j                trip (closure of the main turbine control valves in 2                 about 0.1 to 0.2 sec) are performed at selected j                 power levels. A generator trip is performed at low
:               power level such that steam generation is just
;                 within bypass valve capacity to demonstrate scram
 ;                avoidance. At an intermediate power level,         in i     s          excess of bypass capacity, a turbine trip is                            .
I                 performed, and the response of the plant to this
;                 trip and scram is determined.
L The accident analysis shows the generator trip to
 -                be more limiting than'the turbine trip. Therefore, a generator trip is performed at full rated power.
The trip is initiated by an electrical signal condition indicating a generator trip is required.
The turbine generator       overspeed   response   is monitored. Other parameters, such as reactor power j                 and pressure, are also monitored.
: 4. Acceptance Criteria Level 1                                                              33, (J12
                                                                                        ^
l                 For turbine and generator trips there is a delay of less than 0.1 sec following the beginning          of control or stop valve closure before the beginning 5
of bypass valve opening. The bypass valves are opened to a point corresponding to greater than 80 percent of their capacity within 0.3 sec from the beginning of control or stop valve closure i               motion.
1
  ;               Feedwater system settings prevent flooding of the i                 steam line following these transients.
]                 The    positive   change in vessel dome pressure i                occurring within 30 see after either generator or
 }                turbine trip does not exceed the Level 2 criteria by more than 25 psi.
 -     5 The positive change in simulated heat flux does not
] 3 exceed the Level 2 criteria by more than 2 percent.
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         /vseRr 1
Amendment 5                14.2-168               August 1982              ''
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Insert'for Page 14.2-168 The -low-low set pressure relief logic functions to preclude subsequent simultaneous SRV actuations following the initial SRV actuation due to original pressurization transient.
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   /S 1 12._3,c24 W O(MMb# 29                           RBS FSAR Level 2 There is no MSIV closure during the first 3 min of the transient from low water level, and operator        lt s action is not required during that period to avoid the MSIV trip.
The   positive change in vessel dome pressure and in simulated heat flux which occurs within the first 30 sec after initiation of either generator or turbine trip does not exceed the predicted    values, as   determined by the nuclear engineer at the time of the test.
(NOTE:     Predicted Values are referenced to actual test conditions of initial power level and dome precsure and use beginning-of-life nuclear data.
Worst case design or Technical Specification values of    all hardware performance are used in the prediction, with the exception of control rod          5 insertion time and delay from the beginning of turbine control valve or stop valve motion to the generation of the scram signal.         The predicted pressure and heat flux are corrected for the actual measured values of these two parameters.)
For the generator trip within the bypass valves capacity, the reactor does not scram for initial thermal power levels within that bypass          valve capacity.
Low water level total recirculation       pump trip, HPCS, and RCIC are not initiated.
Feedwater level control avoids loss of feedwater due to a h h level (L8) trip during the event.
       /g 14.2.12.3.25   Test Number 28 - Shutdown From Outside the Main Control Room
: 1. Test Objective The purpose of this test is to demonstrate that the reactor can be brought from a normal initial steady-state power level down to the point where normal low pressure shutdown cooling is initiated and is under control with reactor vessel pressure and water level controlled from outside the main control room.
Amendment 13                  14.2-169                June 1984

    -Insert for Page 14.2-169 When the low-low pressure relief logic functions, the open/close sections.of the SRVs occur within 113 psi and 20 psi, respectively, of.
their design points.
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RBS FSAR 14.2.12.3.27.2   Test Number 30B - Trip of Two Pumps                 s
: 1. Test Objective The purpose of the test is to record and verify acceptable    performance       of  ,the    recirculation two-pump trip.
: 2. Prerequisites The   appropriate   preoperational     tests    have  been completed and the FRC has reviewed and approved the test    procedures    and     initiation      of testing.
Instrumentation has been checked or        calibrated as appropriate.
: 3. Test Procedure Both recirculation pumps are tripped at the desired         s power level, and the flow coastdown transient is recorded.
: 4. Acceptance Criteria Level 1 The two-pump drive flow coastdown transient during s
the first 5 see is equal to or greater inan that               lts g             specified g Fig. 1 " . 2 - 5 ."
14.2.12.3.27.3   Test Number 30C - System Performance               ls
: 1. Test Objective The purpose of this test is to record recirculation system parameters during the power test program.
: 2. Prerequisites The preoperational tests are complete. The FRC has reviewed and approved the test procedures and initiation of testing.          Instrumentation has been checked or calibrated as appropriate.
: 3. Test Procedure Recirculation system parameters          are   recorded at several power-flow conditions and in           conjunction with single pump trip recoveries.
Amendment 16             14.2-177                     February 1985

 .F--
Insert for Page 14.2-177 in General Electric Company's (GE) Transient Safety Analysis Design Report (TSADR).
l ._

TE ST CONOlflONS                                               NOMS TE Sf',
                                  ,,,,,,,,g                 OPEN  MEA 9                                       W AA AANTY      ltp TEST CONoifeONS REFER TO NO                                                 VESSEL  Up 1 l 3 l 3 l 4 l 8 l 8                                    CON 0efl0NS $f ATE 0 0N E                g-                           FIG           4 0F YME FSAR 1    CHEMsCAL ANO AADeOCMEeNCAL                     E     I     I E     I     E          E                E             E              SECTIONS NURSOERS OF SECTION 2    AA08AflON astaSUAtasENT se 213 3 0F THE FSAR 3    FUEL LOADiseG                                  I (3) PERFOnes TEST S. TanisMG OF 4 4    FULL CORE SMuf00WN AAAAGese                    I                                                                    SLOWEST CONTROL ROOS em E     E*          E"              5                            CONJunsCTION WifM EEPECTED S    CONTROL A00 0AlvE SYSTEM                       E SCRAteS S    SAM PE AFOARSANCE                              E                                                               (Al 70 M COG 8PLETED MTWEEN TEST I
CommTWNS t ANO 3 te    Ntas PE AFOAnsANCE                                         E (St AFTEA REC 3AC Putep TAsPS tt    LP Ate C AueAAfl0N                                   K*    r*  3                       m                       (Si 00WN SETPO40sf OesLV I     E   E       I           I   E                       17) NU SVPASS v&Lvt ESPO8eGE 13    APAes CAUSAAflON                                                                                               (9) NO CONTROL WALVE AESPoleH l   13    PROCESS COMPUTER                                     E     r*                          y                       ggi ufWgEN 80's AN0 90% POWER E     E*  Em                                            (10) MTWEEN TEST CONOITIONS S ANO to    ACIC SYSTEas                                                                                                        4 SETWEEN Fett AAs0 00*s POWEA tea    SELECTE0 PROCESS TEMPER ATURES                       I                 E"              M*                    (tt) AT MARIMURO POWER Tataf WeLL AA tag    WATER LEVEL AEF LEG TEMPS                            E                                 E M           A         N f0 TEST CON 0tTIONS ff    SYSTEte EEPA80SION                                   E     K*  I"                                            gt3) MfWggm sgeg AN0 ggg POWER og                                                                           E               I                     (145 MTWEEN SeseANO m OWER inP UseCERT Aa8ITT (19) MTWEEN TEST C0se0sfl0NS 3 ANO E   I       E      E    E   E                            3 19    CORE PERFORMANct I      (188 GMAMA TMAN FSte POWER. Pm 29    STEAM PA00UCTION                                                                                                    tSOLATIOes 31    COPE POWE A VOs0 MODE RESPONSE                                                I    I                         (f t) OENENATOR LOAO REJECYlON.
E   E       E*     I    I   M*
* I'         I         A Il    PRESSURE REGULATOR                                                                                           (tSt TURGessE Thep SCA Ate 89ae YO 90%
234    W ATER LEVEL SETPoemf CMANGES                                  E       E      I    I    I                           POWER af SS% CORE FLOW (1 91                   - GENERATOR 338    FEEDW ATER STS LOSS OF FW nEATHeG                                                      E.
33C    FEE 0W ATER Sfl Puesp TAtr                                                                                   ite) Af STEA0T STATE Ale 0 As E                           I 230    FEE 0 WATER SVS esAE AuseOUT CAPASeuff                                                  E*                                   " ,g yg         gg as    funtiseE v&LvE SUAvteLL AasCE                                          E           F*   E"                          CONOENtesO I I '             '                 '
ISA    Ressv FuseCYtONAL TEST                                E     M* I"'*                f*   I "'
TEST CONOflode S il  358 ISC MSiv FULL CLOSURE asasse STE Ate UNE PLOW VENfuge CAUS                                   E I[M)
E' 1233 SeNGLE v4LVE g',,g
* asas4 STE Ats u888 ELSOW T AP CAug                                      I               E**                   (29) RESposeSE CNECE Ocet?
250 24    AEUEF WALUES                                          E         E*                             -
* OUICE STAATS 0est?
II   3P    fuggeNg Trip 40g0 GENERAf0A LOAO REJECTIO80                 I"         E*               I*.fp)
(27) #NSPECTION AFTER 2NO ANO 3 O TMt         C is    SMUf 00Wes F A0as OUTSa0E C04f A04 AOOM                     E                                                            y gg        gy E, g 23    RECIRCUL&flON FLOW CONTROL                     E            I   I*      5           E*                               CONotitON 3 msfEA0 WECimCULATION STSTEhe ONE PUMP f App                                    I               E 30 4 30 0   AECIACUL AfiON SYSTEM TWO PUMP Tmp                                      E 3eC    RECIACULAft0N SYSTEIA PERFORM &seCE                                     I ^*            I' 30 0  RECIRCULAfiO8e SYSTIns Puesp AuMSACI                                    E act    RECIACUL AfsON Sv$fE as C Avef a fe0m                           E E
I hh 39    LOSS OF 7U89 GENERATOR S OFFtfE PWR 33    ORietLL PtP'NG wigA ATION                             I     E           E*               Ed RECeAcutaficas Sv3 fens FLOW CausAAriOss                                E               E 3s
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'        FS    RE ACTOR Waf ER CLE ANUP STSTEM                       E l
'        FI    RES80UAL ME A T AEMOVAL SYSTEM                        E ''                              I" DATWELL Af tsOSPMERE C00UNG SYSTEM                    E                                  E te3 l        lel   PEseETR Afs0N TEnspg A&funt                           E                                      l l
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l                                                                                           FIGURE 14.2-5 1
STARTUP TEST PROGRAM l
RIVER BEND STATION FINAL SAFETY ANALYSIS REPORT I
!                                                                                         AMENDMENT 17                                                      MARCH 1985 L

4' 1
RBS FSAR
         #g     QUESTION 640.21 (14.2.12.1) 14.2.12.33. Expand  the   Reactor Plant Ventilation System Preoperational test to provide acceptance criteria for those components or processes described in Test Objectives 1.b, 1.c, and 1.e.

===RESPONSE===
The   response to this request is _provided      in   revised Section 14.2.12.1.33g Ak23 14 3.10.l. % .                       ..
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       / "i     Amendment 5                Q&R 14.2-27            August 1982 i
     !                         's                        .

y        m                                                               -
RBS FSAR QUESTION 640.29 (14.2.12.1) 14.2.12.1.47. Expand the Fuel Building Ventilation System Preoperational Test to provide acceptance criteria for the pressure differential between the various areas maintained by the fuel building ventilation system and the outside atmosphere.

===RESPONSE===
The    response    to   this request  is provided in  r: ci c d ''
Section l' . 2.12.1. '7 ?'
F/.2 4 ./. 7 0 Amendment 5                  Q&R 14.2-35          August 1982
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