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| number = ML18283A852
| number = ML18283A852
| issue date = 02/14/1977
| issue date = 02/14/1977
| title = LER 1977-771-00 for Browns Ferry Nuclear Plant, Unit 1, Reservoir Water Temperature Exceeding Maximum Temperature Rise of 5 Degrees F on 02/03/1977
| title = For Browns Ferry Nuclear Plant, Unit 1, Reservoir Water Temperature Exceeding Maximum Temperature Rise of 5 Degrees F on 02/03/1977
| author name = Gilleland J
| author name = Gilleland J
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:U.S. NUCLEAR REGULATORY Co   ION DOCKET NUMBER NRC FORM 195 (2-7B) C                                                                                      o- re(
{{#Wiki_filter:NRC FORM 195 (2-7B) C U.S. NUCLEAR REGULATORY Co ION DOCKET NUMBER o-re(
FI E NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO:       Mr   N C Moseley                     FROM: Tennessee     Valley Authority     DATE OF DOCUMENT Chattanooga,    Tn                            2-14-77 J  E  Gilleland                  DATE RECEIVED 2-23-77
FI E NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL
@LETTER                    CINOTORIZED          PROP                  INPUT FORM        NUMBER OF COPIES RECEIVED QORIGINAL              IRUNCLASSIFIE 0 3ICOP Y lcc DESCRIPTION                                                      ENCLOSURE Ltr trans the following:                                       Licensee Event Report (RO/II 771) on 2-3-77 which concerni Appendix B violation with regard to reservoir water temperature exceedin tech specs limitations.......
@LETTER QORIGINAL 3ICOP Y DESCRIPTION CINOTORIZED IRUNCLASSIFIE0 TO:
lp ppgg,Q Q$)~pp PLANT       NAME'rowns Ferry FOR ACTION/INFORMATION
Mr N C Moseley PROP INPUT FORM ENCLOSURE FROM: Tennessee Valley Authority Chattanooga, Tn J
                                                                                              -  7          ehf ASSIGNED AD!
E Gilleland DATE OF DOCUMENT 2-14-77 DATE RECEIVED 2-23-77 NUMBER OF COPIES RECEIVED lcc Ltr trans the following:
PROJECT MANAGER!
lp Licensee Event Report (RO/II 771) on 2-3-77 which concerni Appendix B violation with regard to reservoir water temperature exceedin tech specs limitations.......
L    C    ASS    !                                              LIC ASST INTERNAL DISTRIBUTION G.-,FI                         SYSTEMS SAFETY                PLANT SYSTEMS            S            SA NRC PDR                             HEINEMAN                      TEDESCO X&E 2                             SCHROEDER OELD GOSSXCK & STAFF                     ENGXNEERING                  IPPOLITO MIPC                               MACARR                                                  ERNST CASE                               BOSNAK                                                  BALLARD HANAUER                             SIHWEIL                      OPERATING REACTORS        SPANGLER HARLESS                             PAWL CK                      STELLO SITE TECH PROJECT MANAGEMENT                 REACTOR SAFE                  OPERATING TECH            GAMMILL BOYD                               ROSS                          EXSENHUT                  STEPP PE COLLINS                         NOVAK                                                  HULMAN HOUSTON                             ROSZTOCZY PETERSON                           CHECK                        B    E                    SITE ANALYSIS MELTZ                                                                                       VOLLMER HELTEMES                           AT & I                                                 J SKOVHOLT                            SALTZMAN                                                   COLLINS'REGER RUTBERG EXTERNAL DISTRIBUTION                                        CONTROL NUMBER LPDR.                            NAT LAB                       B 00 TIC!                              REG V IE                     ULR KSON    0 NSIC!                            LA PDR ASLB!                              CONSULTANTS!   I ACRS        CYS  3KLQXHC/
Q$)~pp ppgg,Q PLANT NAME'rowns Ferry ASSIGNED AD!
FOR ACTION/INFORMATION 7
ehf L C ASS PROJECT MANAGER!
LIC ASST INTERNALDISTRIBUTION G.-,FI NRC PDR X&E 2
OELD GOSSXCK & STAFF MIPC CASE HANAUER HARLESS PROJECT MANAGEMENT BOYD PE COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR.
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SYSTEMS SAFETY HEINEMAN SCHROEDER ENGXNEERING MACARR BOSNAK SIHWEIL PAWL CK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT & I SALTZMAN RUTBERG EXTERNALDISTRIBUTION NAT LAB REG V IE LA PDR CONSULTANTS! I PLANT SYSTEMS TEDESCO IPPOLITO OPERATING REACTORS STELLO OPERATING TECH EXSENHUT B
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S SA ERNST BALLARD SPANGLER SITE TECH GAMMILL STEPP HULMAN SITE ANALYSIS VOLLMER J
COLLINS'REGER CONTROL NUMBER


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          -'6g               ~,.             830   P<FFFF.r Building TENNESSEE VALLEY AUTHORlTY CHATTANOOGA, TENNESSEE 37401 5~
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b                                          February 14, 1977 "PPS.1@+
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Ih. Norman C. HoseleyDirector               ~;.~jq jlgig~~>> gOCIrtef It Nuclear Regulatory Commission                                        III'.S.
830 P<FFFF.r Building TENNESSEE VALLEYAUTHORlTY CHATTANOOGA, TENNESSEE 37401 February 14, 1977 Ih. Norman C. HoseleyDirector
Region     II 230 Peachtree Street, Rf., Suite 1217 Atlanta,, Georgia 30303
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gOCIrtef It III'.S.
Nuclear Regulatory Commission Region II 230 Peachtree Street, Rf., Suite 1217 Atlanta,, Georgia 30303


==Dear     Nr; Moseley:==
==Dear Nr; Moseley:==
TENNESSEE V~ AUTHORITY BROWS FERRY NtJCLEAR PLQF2 UNXT 1-DOCKET NO. 50-259 - FACILXTY OPERATING LICENSE DPR-33 ENVIRON-MENTAL REPORTABLE OCCUREKNCE BFERO-50-259/773, The enclosed. report is to provide details concerning the reservoir vater temperature
.exceeding the maximum temperature rise of 5 degrees F on February 3, 1977.
This report supplements our telecopy to you on February 3, 1977, from H. J. Green, This report is submitted i.n accordance vith Brovns Ferry Technical Specgfication 5.6.3b.
This event occurred on Brovns Ferry Nuclear Plant unit 1.
Very truly yours',
J. E. GilloFland Assistant Ravager of'over
~if I gA,'y Enclosure (3)
IF CC (Enclosure):
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. Director Division of Operating Reactors o'~Zg
~ U.S. Nuclear Regulatory Commission
: 19pp, ltashington, DC 20555 co Ig Pg Director (3)
Office of Management Information and. Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Director (40)
Office of Xnspection and, Enforcement U.S, Nuclear Regulatory Commission Uashington, DC 20555 An Equal Opportunity Employer CP~+~oO
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TENNESSEE      V~
,+II III(AA /
DOCKET NO. 50-259 AUTHORITY BROWS FERRY NtJCLEAR PLQF2 UNXT FACILXTY OPERATING LICENSE DPR-33 ENVIRON-1-
j, l
MENTAL REPORTABLE OCCUREKNCE BFERO-50-259/773, The enclosed. report is to provide details concerning the reservoir vater temperature .exceeding the maximum temperature rise of 5 degrees F on February 3, 1977. This report supplements our telecopy to you on February 3, 1977, from H. J. Green, This report is submitted i.n accordance vith Brovns Ferry Technical Specgfication 5.6.3b. This event occurred on Brovns Ferry Nuclear Plant unit 1.
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Very  truly yours',
J. E. GilloFland Assistant Ravager    of'over Enclosure (3)                                                IF
                                                                                                                'y
                                                                                                          ~if I gA, CC  (Enclosure):
                      . Director                                                                      g /p Division of Operating Reactors                                    o'~Zg
                    ~
U.S. Nuclear Regulatory Commission                                                    19pp, co ltashington, DC  20555                                                          Ig  Pg Director (3)
Office of Management Information          and. Program    Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Director (40)
Office of Xnspection    and, Enforcement U.S, Nuclear Regulatory Commission Uashington, DC 20555                                              CP~+~oO
                                                                                                                -3
                                                                                          ,CS An Equal Opportunity Employer


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t; L%NSEE EVENT.
                      /
e CONTI40L BLOCI(:~J LICLNCEE NAMI.
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LICENSE NUMLIEll Ioe'L LA~La~nF 1
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7 09 14 15 REPORT LICENSE TYPE EVENT TYPE 0
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25 26 30 31 32 (PLEASE PRINT ALLREOUIREO INFORMATION)
RE PI!AT AEVI!
A'A'TCOORY TYPE SOUIICE OOCSE'T NUMOER EVCNT DATE
~01 coN'T~
~T L
0 5
0 0 2
5 9
0 2
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50 59 60 61 68 69 74 EVENT OESCR!PTION I002".~l Attachment 75 REPORT DATE 0 elI 7
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[cC 0 9 toOGI 'L 0 9 SYSTEM CAUSE COOL CODE COMPONENT CODE
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Z "Z 8 9 10 11 12 CAUSE DESCRIPTION gg ~Attaclment 8 9
;Oft.89
~TH l PAME COMPONENT SUPPUEA 17 43 COMPOI4FN7 MANUFACTURER 9
9 9
44 47 Y
48 eo 80 8 9 FACILITY STATUS PDWEA OTHER STATUS 3Qi
~E
~09 4
II A 0
9 10 12 13 FOAM OF ACTIVAY CON TENT ALLFASEO OF RELEASE AMOUNT OF ACTIVITY A
NA 0
s 10 11 PERSONNEL EXPOSURES 89 11 12 10 PERSONNEL INJUR!ES 89
'l1 12 OFFSITE CONSEQUENCES 1+5 LN AA 0 9 LOSS OR DAMAGE TO FACILITY TgPE OCSCAIPTION K~l L~J LN A 09 1G PUBLICliY ig)L NA 09 ADDITIONAL FACTORS i
I Atteolvaent 89 METHOD OF DISCOVEAY A
44 45 46 44 45 DISCOVERY DESCRIPTION LOCATION OF RELEASE 6G ec 80 80 85 00 00


t; L%NSEE            EVENT. REPORT e
Report No.:
CONTI40L      BLOCI(:~ J                                                              (PLEASE PRINT ALL REOUIREO INFORMATION)
BFHRO-50-259/771 Report Date:
LICLNCEE                                                                                          LICENSE              EVENT NAMI.                                        LICENSE NUMLIEll                                    TYPE                TYPE Ioe'L    LA~La~nF                      1      ~OO            L~OO          O O      O        0    0          4    1    1    1  1      L0oo4~!
February 14, 1977 Occurrence Date:
                    ~
February 3, 1977 Facility:
7    09                                  14     15                                                    25      26                  30    31      32 RE PI!AT  AEVI!
Browns Ferry Nuclear Plant EVENT DESCRIPTION On February 3, 1977, from 0929 to 1129 hours, the reservoir water temp'erature exceeded the maximum temperature rise of 5 degrees F.
SOUIICE                  OOCSE'T NUMOER                            EVCNT DATE                      REPORT DATE TYPE 7774 A'A'TCOORY
The maximum value was 6.2 degrees F occurring at 1029 hours.
  ~01 coN'T                          ~T          L            0  5   0    0        2   5    9          0    2    0  3 7    8            5/      50      59        60            61                                  68    69  "
The maximum downstream temperature was 43 degrees F.
75 EVENT OESCR!PTION INl 7
(BFHRO-50-259/771)
I002".~l 7
CAUSE DHSCRIPTION A computer program, which is run daily, calculates for the next 24-hour period hourly values of maximum temperature and temperature rise in the reservoir as a function of scheduled nuclear and hydro plant generation levels and recommends to the Browns Ferry plant operator the most economical combination of condenser cooling at the plant.
0 0 9 0 0 el Attachment eo 80
Releases from Guntersville and Wheeler Hydro Plants had'een fairly steady from 1800 hours until 2300 hours on February 2 at rates that produced river flows in excess of 20,000 cfs.
[cC 0 9 toOGI  'L 0 9                                                                        PAME SYSTEM      CAUSE                                               COMPONENT              COMPOI4FN 7 MANUFACTURER
The hydro discharges were then reduced at 2400 hours and held at very low flows until 0500 hours on February 3.
[oa~]      ~ZZ COOL        CODE A             Z COMPONENT CODE Z          Z  "Z              SUPPUEA 9    9    9              Y 8 9 10                  11        12                              17        43          44                    47          48 CAUSE DESCRIPTION gg8 9~Attaclment
The computer program was not updated to reflect a change in hydro plant generation or the plant notified of this change.
;Oft.
As a result, the river temperature rise exceeded 5 degrees F before appropriate action at Browns Ferry could be taken to avoid it.
89
Water temperature at the time of the streamflow reduction was 40.5 degrees F downstream with an indicated Delta T of 3.3 degrees F.
  ~TH l
8 9                                                                                                                                                      6G FACILITY                                                                METHOD OF STATUS                PDWEA                      OTHER STATUS          DISCOVEAY                          DISCOVERY DESCRIPTION 3Qi            ~E              ~09        4                II A                          A 0        9                10            12 13                                44    45        46 FOAM OF ACT IVAY        CON TENT ALLFASEO      OF RELEASE                  AMOUNT OF ACTIVITY                                                LOCATION OF RELEASE A            NA 0          s                10      11                                        44      45                                                              ec PERSONNEL EXPOSURES 89                  11      12      10 PERSONNEL INJUR!ES 89                  'l1  12                                                                                                                            80 OFFSITE CONSEQUENCES 1+5     LN      AA 0 9 LOSS OR DAMAGE TO FACILITY TgPE          OCSCAIPTION K~l L~J              LN A 09              1G                                                                                                                                      80 PUBLICliY ig)L09 NA 85 ADDITIONAL FACTORS i      I    Atteolvaent 89                                                                                                                                                      00 00


Report No.:    BFHRO-50-259/771 Report Date:    February 14, 1977 Occurrence Date:       February 3, 1977 Facility:    Browns   Ferry Nuclear Plant EVENT DESCRIPTION On  February 3, 1977, from 0929 to 1129 hours, the reservoir water temp'erature exceeded  the maximum temperature rise of      5  degrees F. The maximum value was 6.2 degrees F occurring at 1029 hours.        The maximum downstream temperature was 43 degrees    F.   (BFHRO-50-259/771)
The Browne Ferry plant condenser cooling operating mode is scheduled in advance by the computer calculation.
CAUSE DHSCRIPTION A computer program, which      is run daily, calculates for the next 24-hour period hourly values of      maximum  temperature and temperature rise in the reservoir as a  function of scheduled nuclear      and hydro  plant generation levels    and recommends    to the Browns Ferry plant operator the most economical combination of condenser cooling at the plant.
When the February 3 schedule was developed on February 2, river flows were predicted to be "adequate for condenser cooling at Browns Ferry.
Releases  from Guntersville and Wheeler Hydro Plants had'een          fairly steady from 1800 hours    until  2300 hours on February 2    at rates that produced river flows in excess of 20,000 cfs.       The hydro  discharges were then reduced at 2400 hours and held      at very low flows until    0500 hours on February 3. The computer program was not updated to       reflect  a change  in hydro plant generation or the plant notified of this change.        As a  result, the river temperature rise  exceeded  5  degrees F before appropriate action at Browns Ferry could be taken to avoid    it. Water temperature  at the time of the streamflow reduction was 40.5 degrees      F downstream  with  an indicated Delta    T  of 3.3 degrees F.
: However, the Guntersville and Wheeler Hydro Plants were shut down during the night of February 2, resulting in greatly reduced river flows.
Browns Ferry personnel were not notified of this situation, so Browns Ferry continued to operate at the predicted load.
The temperature increase was detected by'he downstream monitors after'he river flow was reestablished.
DHSIGNATION OF APPARHNT CAUSH OF OCCURRHNCH River flow was not maintained according to the predicted schedule.
When the change was made, Browne Ferry personnel were not notified.
CORRHCTIVH ACTION When the plant superintendent noticed the rapid increase in the river temper-ature rise, he called the assistant chief load dispatcher in Chattanooga to xequest more river flow.
He was then informed of the decreased river flow that had occurred a few hours earlier and was advised that river flow had already been increased to a level that should assist in maintaining temperatures less than the 5 degrees F limit.
Therefore, plant load was not reduced.
In order to prevent future occurrences of this type, the plant operator will be notified immediately by the load coordinator of significant deviations from the predicted river flow as required by existing procedures.
Using this information, the plant operating personnel will select the optimum


The Browne  Ferry plant condenser cooling operating        mode is  scheduled  in advance by the computer  calculation. When  the February  3  schedule was developed on February 2,  river flows    were predicted to be "adequate    for condenser cooling at Browns Ferry.      However, the  Guntersville  and Wheeler Hydro Plants were shut down during the        night of February 2, resulting in greatly reduced river flows.      Browns  Ferry personnel were not notified of this situation,  so Browns  Ferry continued to operate at the predicted load.
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The temperature  increase was detected    by'he    downstream monitors  after'he river flow was reestablished.
DHSIGNATION OF APPARHNT CAUSH OF OCCURRHNCH River flow  was  not maintained according to the predicted schedule.          When the change was made, Browne Ferry personnel were not          notified.
CORRHCTIVH ACTION When  the plant superintendent noticed the rapid increase        in the river temper-ature rise, he called the assistant chief load dispatcher in Chattanooga to xequest more river flow. He was then informed of the decreased river flow that  had occurred a few hours    earlier  and was advised    that river flow had already been increased    to  a  level that should assist in maintaining temperatures  less than the  5  degrees F  limit. Therefore, plant load  was not reduced.
In order to prevent future occurrences of this type, the plant operator            will be  notified immediately  by the load    coordinator of significant deviations from the predicted    river flow as required    by  existing procedures. Using this information, the plant operating personnel          will select  the optimum


C condenser cooling modes to ensure compliance with the technical speci-fications. The importance of following this procedure has been reemphasized to the plant operators and the Power System Load Coordinator.
condenser cooling modes to ensure compliance with the technical speci-fications.
The importance of following this procedure has been reemphasized to the plant operators and the Power System Load Coordinator.


Table 1 ANALYSIS Ol'IVER VATER TE".PERATURE DATA BEFORE AND POLLOllPilG OCCURRENCE Temperature                    Guntersville  Wheeler Date and Time       Dovnstream     Delta   T     Dischar e   Discharge CST                              OP                      '100   CPS 2/2/77,   1900 Hrs.                                     443          419 2000                                           332          303
Table 1
        '2100                                           322         300 2200                                          212         272 2300                                          175         233 2400                                          112         ill 2/3 /77, 0100           40.5             3.3             26          14 0200          40.3             3.0               0           0 0300          40.3             2.9               0            0 0400          40.2            3.0             90          83 0500          40.3             3.5             214          178 0600          40.7            4.2             214          178 0700          41.0            4.6             442          461 0800          40.8            4'             491        ,586 0829          41.0.            4,4 0900          41.4            4.8             488,        592 0914          41.7            5,0 0929          41.9            5.2 0944          42.. 1          5.4 0959          42.4            5,7                         583 1014          42.8            6.0 1029          43,0            6.2 1044          42.9            6.1 1059          42.7            5.9             512          536 1114          42o3            5.4 1129          41.8            4.9 1144          41.3            4, lt 1159          40. 9            4.0             507 1214         40. 5           3' 1229          40.0             3.0}}
ANALYSIS Ol'IVER VATER TE".PERATURE DATA BEFORE AND POLLOllPilG OCCURRENCE Date and Time CST Temperature Dovnstream Delta T OP Guntersville Dischar e
Wheeler Discharge
'100 CPS 2/2/77, 1900 Hrs.
2000
'2100 2200 2300 2400 443 332 322 212 175 112 419 303 300 272 233ill 2/3/77, 0100 0200 0300 0400 0500 0600 0700 0800 0829 0900 0914 0929 0944 0959 1014 1029 1044 1059 1114 1129 1144 1159 40.5 40.3 40.3 40.2 40.3 40.7 41.0 40.8 41.0.
41.4 41.7 41.9 42.. 1 42.4 42.8 43,0 42.9 42.7 42o3 41.8 41.3
: 40. 9 3.3 3.0 2.9 3.0 3.5 4.2 4.6 4 '
4,4 4.8 5,0 5.2 5.4 5,7 6.0 6.2 6.1 5.9 5.4 4.9 4, lt 4.0 26 0
0 90 214 214 442 491
: 488, 512 507 14 0
0 83 178 178 461
,586 592 583 536 1214 1229
: 40. 5 40.0 3 '
3.0}}

Latest revision as of 12:28, 5 January 2025

For Browns Ferry Nuclear Plant, Unit 1, Reservoir Water Temperature Exceeding Maximum Temperature Rise of 5 Degrees F on 02/03/1977
ML18283A852
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 02/14/1977
From: Gilleland J
Tennessee Valley Authority
To: Moseley N
NRC/RGN-II
References
Download: ML18283A852 (13)
v • d • e


Text

NRC FORM 195 (2-7B) C U.S. NUCLEAR REGULATORY Co ION DOCKET NUMBER o-re(

FI E NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL

@LETTER QORIGINAL 3ICOP Y DESCRIPTION CINOTORIZED IRUNCLASSIFIE0 TO:

Mr N C Moseley PROP INPUT FORM ENCLOSURE FROM: Tennessee Valley Authority Chattanooga, Tn J

E Gilleland DATE OF DOCUMENT 2-14-77 DATE RECEIVED 2-23-77 NUMBER OF COPIES RECEIVED lcc Ltr trans the following:

lp Licensee Event Report (RO/II 771) on 2-3-77 which concerni Appendix B violation with regard to reservoir water temperature exceedin tech specs limitations.......

Q$)~pp ppgg,Q PLANT NAME'rowns Ferry ASSIGNED AD!

FOR ACTION/INFORMATION 7

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LIC ASST INTERNALDISTRIBUTION G.-,FI NRC PDR X&E 2

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SYSTEMS SAFETY HEINEMAN SCHROEDER ENGXNEERING MACARR BOSNAK SIHWEIL PAWL CK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT & I SALTZMAN RUTBERG EXTERNALDISTRIBUTION NAT LAB REG V IE LA PDR CONSULTANTS! I PLANT SYSTEMS TEDESCO IPPOLITO OPERATING REACTORS STELLO OPERATING TECH EXSENHUT B

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Nuclear Regulatory Commission Region II 230 Peachtree Street, Rf., Suite 1217 Atlanta,, Georgia 30303

Dear Nr; Moseley:

TENNESSEE V~ AUTHORITY BROWS FERRY NtJCLEAR PLQF2 UNXT 1-DOCKET NO. 50-259 - FACILXTY OPERATING LICENSE DPR-33 ENVIRON-MENTAL REPORTABLE OCCUREKNCE BFERO-50-259/773, The enclosed. report is to provide details concerning the reservoir vater temperature

.exceeding the maximum temperature rise of 5 degrees F on February 3, 1977.

This report supplements our telecopy to you on February 3, 1977, from H. J. Green, This report is submitted i.n accordance vith Brovns Ferry Technical Specgfication 5.6.3b.

This event occurred on Brovns Ferry Nuclear Plant unit 1.

Very truly yours',

J. E. GilloFland Assistant Ravager of'over

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Office of Management Information and. Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Director (40)

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Report No.:

BFHRO-50-259/771 Report Date:

February 14, 1977 Occurrence Date:

February 3, 1977 Facility:

Browns Ferry Nuclear Plant EVENT DESCRIPTION On February 3, 1977, from 0929 to 1129 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.295845e-4 months <br />, the reservoir water temp'erature exceeded the maximum temperature rise of 5 degrees F.

The maximum value was 6.2 degrees F occurring at 1029 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.915345e-4 months <br />.

The maximum downstream temperature was 43 degrees F.

(BFHRO-50-259/771)

CAUSE DHSCRIPTION A computer program, which is run daily, calculates for the next 24-hour period hourly values of maximum temperature and temperature rise in the reservoir as a function of scheduled nuclear and hydro plant generation levels and recommends to the Browns Ferry plant operator the most economical combination of condenser cooling at the plant.

Releases from Guntersville and Wheeler Hydro Plants had'een fairly steady from 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on February 2 at rates that produced river flows in excess of 20,000 cfs.

The hydro discharges were then reduced at 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> and held at very low flows until 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on February 3.

The computer program was not updated to reflect a change in hydro plant generation or the plant notified of this change.

As a result, the river temperature rise exceeded 5 degrees F before appropriate action at Browns Ferry could be taken to avoid it.

Water temperature at the time of the streamflow reduction was 40.5 degrees F downstream with an indicated Delta T of 3.3 degrees F.

The Browne Ferry plant condenser cooling operating mode is scheduled in advance by the computer calculation.

When the February 3 schedule was developed on February 2, river flows were predicted to be "adequate for condenser cooling at Browns Ferry.

However, the Guntersville and Wheeler Hydro Plants were shut down during the night of February 2, resulting in greatly reduced river flows.

Browns Ferry personnel were not notified of this situation, so Browns Ferry continued to operate at the predicted load.

The temperature increase was detected by'he downstream monitors after'he river flow was reestablished.

DHSIGNATION OF APPARHNT CAUSH OF OCCURRHNCH River flow was not maintained according to the predicted schedule.

When the change was made, Browne Ferry personnel were not notified.

CORRHCTIVH ACTION When the plant superintendent noticed the rapid increase in the river temper-ature rise, he called the assistant chief load dispatcher in Chattanooga to xequest more river flow.

He was then informed of the decreased river flow that had occurred a few hours earlier and was advised that river flow had already been increased to a level that should assist in maintaining temperatures less than the 5 degrees F limit.

Therefore, plant load was not reduced.

In order to prevent future occurrences of this type, the plant operator will be notified immediately by the load coordinator of significant deviations from the predicted river flow as required by existing procedures.

Using this information, the plant operating personnel will select the optimum

C

condenser cooling modes to ensure compliance with the technical speci-fications.

The importance of following this procedure has been reemphasized to the plant operators and the Power System Load Coordinator.

Table 1

ANALYSIS Ol'IVER VATER TE".PERATURE DATA BEFORE AND POLLOllPilG OCCURRENCE Date and Time CST Temperature Dovnstream Delta T OP Guntersville Dischar e

Wheeler Discharge

'100 CPS 2/2/77, 1900 Hrs.

2000

'2100 2200 2300 2400 443 332 322 212 175 112 419 303 300 272 233ill 2/3/77, 0100 0200 0300 0400 0500 0600 0700 0800 0829 0900 0914 0929 0944 0959 1014 1029 1044 1059 1114 1129 1144 1159 40.5 40.3 40.3 40.2 40.3 40.7 41.0 40.8 41.0.

41.4 41.7 41.9 42.. 1 42.4 42.8 43,0 42.9 42.7 42o3 41.8 41.3

40. 9 3.3 3.0 2.9 3.0 3.5 4.2 4.6 4 '

4,4 4.8 5,0 5.2 5.4 5,7 6.0 6.2 6.1 5.9 5.4 4.9 4, lt 4.0 26 0

0 90 214 214 442 491

488, 512 507 14 0

0 83 178 178 461

,586 592 583 536 1214 1229

40. 5 40.0 3 '

3.0

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