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{{#Wiki_filter:U S, NUCLEAR REGULATORv COMMISSION t NRC FoRM 195 IZ-7B)'p NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL DOC T UMB FILE NUMBER ETTER RIG INAL OPY DESCRIPTION 0 OTOR IZED UNCLASSIFIED TO:,'Norman C.Noseley PROP INPUT FORM ENCLOSURE FROM: Tennessee Valley Authority Chattanooga, Tenn H.S.Fox DATE OF DOCUMENT 7/14/77 DATE RECEIVED 7/18/77 NUMBER OF COPIES RECEIVED I e'OZOV@F>0 y,CKZOWLEDG<D PLANT NAIIE:Browns Ferry Nuclear Plant Unit No.3 RBT 7/19/77 Licensee Event Report (50-296/77-8) on 6/21/77 concevhing the releif valve on the discharge of standby liquid control pump 3A which opened at low pressure and stuck in a partially open position during conduct of SI 4.4.A.1.1p++5p FOR ACTION/I NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KRE~R/J.COLLINS ENGC Re~'FO RMATIO INTERNAL D IST Rl BUTION L T EXTERNAL DISTRIBUTION CONTROL NUMBER ACRS 16 SENT AS AT 4 F a h v',~~I"V I a, f t l.
{{#Wiki_filter:NRC FoRM IZ-7B)
Ol UTIOy 6~o~F'-'~)6-~9<~JUL 14]977~0 TENNESSEE VALLEY AUTHORITY CHATTANOOGA.
        '
TENNESSEE 37401 Hr.Norman C.Hoseley irector U.S.Nuclear Regul ry Comndssion Office of Inspec on and Enforcement Region II 230 Peachtre Street, NM<, Suite 1217 Atlanta, rgia 30303~s...v.'-ZK!&TENNESSEE VALLEY AUTHORITY-BROGANS PERRY NUCLEAR PLANT UNIT 3-DOCKET'NO, 50-296-PACD ITY OPERATING LICENSE DPR&8-REPORTABLE OCCURRPNCE REPORT BPRO-50-296/778 The enclosed report is to provide details concerning the relief valve on the discharge of standby liquid control pump 3A vhich vas observed to open at 1300 psig instead of the designed setting of 1400 psig and which stuck in a partially open position during performance of SI 4.4.A.1;This report is submitted in accordance uith Brooms Fe~Technical Specifications Section,6.
p 195 t              U S, NUCLEAR REGULATORv COMMISSION NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL DOC   T UMB FILE NUMBER TO:,       '
This event occurred on Brovns Ferry unit 3.Very truly yours, TENNESSEE VALLEY AUTHORITY H.S.Pox Director of Power Production Enclosure (3)cc (Enclosure)
FROM:                                      DATE OF DOCUMENT Norman C. Noseley                         Tennessee   Valley Authority             7/14/77 Chattanooga,   Tenn                   DATE RECEIVED H. S. Fox                               7/18/77 ETTER                0  OTOR IZED        PROP                  INPUT FORM          NUMBER OF COPIES RECEIVED RIG INAL            UNCLASSIFIED OPY                                                                                I     e DESCRIPTION                                                    ENCLOSURE Licensee Event Report (50-296/77-8) on 6/21/77 concevhing the   releif valve on the discharge of standby liquid control pump 3A
Director (3)Office of Hanagement Information a U.S.Nuclear Regulatory Commissio washington~
                  'OZOV @F>0                                    which opened at low pressure and stuck in a partially open position during conduct of SI 4.4.A.1.
D.C.20555 Director (40)Office df Xnbgoqtion.~tag) gqgorceme U.S.Nuclear Regulatory Cd'sion Washington, D.C.20555 d Program Control.An Equal Opportunity Employer V~('he tlat hf N I r f(,N H N"I , hl't, I I,''h fl I N f f, r f'It h'I I-Ih lh h J I Ih, (I Nl VI f I)hl N Irg'f gl h'P I h'Ol n ns 8i vi'~N~,',*NQJQ Qh PP I Nehlghg J N N Lt4~WtlGCO u>Fi~ba8  
y,CKZOWLEDG<D                              1p++ 5p PLANT NAIIE:Browns      Ferry Nuclear Plant Unit No. 3 RBT  7/19/77 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KRE~R/J. COLLINS ENGC           Re~'FO FOR ACTION/I      RMATIO INTERNAL D IST Rl BUTION L T EXTERNAL DISTRIBUTION                                     CONTROL NUMBER ACRS     16   SENT AS   AT 4   F         a
~LICENSEE EVENT REPORT 4~01 A L 7 89 CONTROL BLOCK: 1 LCENSEE NAME B R F 3 0 14 15 LCENSE NUMBER 0-0 0 0 0 0-0 EVEN~TYF+LCENSE TYPE 0 4 1 1 1 1 0 25 26 30 31 (PLEASE PRINT ALL REQUIRED INFORIVIATIDN)
 
REPORT REPORT CATEGORY TYPE SOURCE[os]coMv~7 8 57 58 59 60 EVENT DESCRIPTION
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[Oar]7 8 9[OO~]7 89 top~]7 8 9 toom DOCKET NUMBER 0 5 0-0 2 9 6 68 (SEE ATTACHED)EVENT DATE REPORT DATE 0 6 2 1 7 7 69 74 75 80 80 80 80 7 89 QOQ 7 89 SYSTEM CAUSE CODE CODE COMPONENT CODE Icos~I~coo o~o ov A L v E x 7 8 9 10 11 12 17 CAUSE DESCRIPTION
          ~   ~
[OOe]PRME COMPONENT SUPPLER N 43 44 C 7 1 0 LNI 47 48 80 80 7 89[OO~]7 89 (SEE ATTACHED)80 80 7 89 FACIUTY S'TATUS TO POWER OTHER STATUS~11~E~06 5 NA 7 8 9 10 12 13 FORM OF ACTIVITY COATENT RELEASED OF RELEASE AMOUNT OF ACTIVITY~a~H~a NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION P~~j~oo o~o 7 89 11 12 13 PERSONNEL IN JURIES NUMBER DESCRIPTION
I           "V I
~4~oo o 7 89 11 12 OFFSITE CONSEQUENCES 7 89 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION
a, f
~a 7 89 10 PUBLICITY 7 89 ADDITIONAL FACTORS tj1I 7 89 7 89 NAME'ETHOD OF DISCOVERY B 44 45 46 44 45 NA NA NA NA NA NA NA PHONE'ISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 80 80 80 80 80 80 80 80 80 GPO 001~007 3~q~>v~E'$~
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C"'NORTHERN STATES POWER COMPANY 00/t t'Il M I NNKA POLI S.'M I NN 5 SQTA'55401 l)gf July<<13, 1977 t Mr J G Keppler, Director, Region III Office of'nspection 6 Enforcement U S,Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137  
 
Ol UTIOy 6~                   ~
TENNESSEE VALLEY AUTHORITY 0
o~
F'                   CHATTANOOGA. TENNESSEE 37401
  - '~)6-~9<~
JUL 14 ]977 Hr. Norman C. Hoseley     irector U.S. Nuclear Regul         ry Comndssion Office of Inspec on and Enforcement Region   II 230 Peachtre     Street,   NM<, Suite 1217 Atlanta,       rgia 30303
                                                          ~s... v. '-     ZK!&
TENNESSEE VALLEY AUTHORITY       - BROGANS PERRY NUCLEAR PLANT UNIT   3-DOCKET 'NO, 50-296   - PACD ITY OPERATING LICENSE DPR&8         - REPORTABLE OCCURRPNCE REPORT BPRO-50-296/778 The enclosed report is to provide details concerning the relief valve on the discharge of standby liquid control pump 3A vhich vas observed to open at 1300 psig instead of the designed setting of 1400 psig and which stuck in a partially open position during performance of SI 4.4.A.1; This report is submitted in accordance uith Brooms             Fe~
Technical Specifications Section,6. This event occurred on Brovns Ferry unit 3.
Very   truly yours, TENNESSEE VALLEY AUTHORITY H. S. Pox Director of     Power Production Enclosure (3) cc (Enclosure)
Director (3)
Office of Hanagement Information         a d Program Control.
U.S. Nuclear Regulatory Commissio washington~ D.C. 20555 Director (40)
Office df Xnbgoqtion.~tag)   gqgorceme U.S. Nuclear Regulatory     Cd 'sion Washington, D.C. 20555 An Equal Opportunity Employer
 
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                                                  ~     LICENSEE EVENT REPORT                         4 CONTROL BLOCK:                                                                 (PLEASE PRINT ALL REQUIRED INFORIVIATIDN) 1 LCENSEE                                                                                   LCENSE                EVEN~
NAME                                     LCENSE NUMBER                                  TYPE                  TYF+
  ~01    A    L    B R       F     3         0   0   0       0   0   0   0   0       0     4     1   1   1   1         0 30
              ~
7  89                              14    15                                              25   26                           31 REPORT       REPORT                                                                                    REPORT DATE CATEGORY                   SOURCE             DOCKET NUMBER                        EVENT DATE
[os]coMv TYPE 0    5  0      0    2 9      6        0  6    2  1    7 7 7   8       57     58         59       60                                         68    69                      74    75                      80 EVENT DESCRIPTION
[Oar]
7 8 9 80
[OO~]
7   89                                                                                                                                             80 (SEE ATTACHED) top~]
7 8 9                                                                                                                                               80 toom 7 89                                                                                                                                                80 QOQ 89                                                                                                                                              80 7
7 SYSTEM CODE Icos~I~coo 8 9 10 o~o       ov CAUSE CODE 11          12 COMPONENT CODE A   L v     E   x 17 PRME COMPONENT SUPPLER N
43           44 C   7   1 0 47 LNI 48 CAUSE DESCRIPTION
[OOe]
7   89                                                                                                                                             80 (SEE ATTACHED)
[OO~]
7   89                                                                                                                                             80 7   89                                                                                                                                             80 FACIUTY                                                                       OF S'TATUS             TO POWER                 OTHER STATUS         DISCOVERY                                  DESCRIPTION
~11         ~E             ~06           5                 NA                    B                                NA 7   8     9             10               12 13                           44    45      46                                                      80 FORM OF ACTIVITY       COATENT RELEASED     OF RELEASE               AMOUNT OF ACTIVITY                                           LOCATION OF RELEASE
                            ~a                           NA                                                        NA
~a        ~H 80 7   8     9               10       11                                   44      45 PERSONNEL EXPOSURES NUMBER           TYPE         DESCRIPTION P~~j   ~oo       o       ~o                                                 NA 80 7 89                 11     12       13 PERSONNEL INJURIES NUMBER           DESCRIPTION
~4 ~oo           o                                                           NA 80 7   89             11   12                                                                         PHONE'ISCOVERY 7    89 NAME'ETHOD OFFSITE CONSEQUENCES NA 80 LOSS OR DAMAGE TO FACILITY TYPE     DESCRIPTION
        ~a                                                                     NA 7   89         10                                                                                                                                   80 PUBLICITY NA 7   89                                                                                                                                             80 ADDITIONAL FACTORS NA tj1I                                                                                                                                                 80 7   89 NA 7   89                                                                                                                                             80 GPO 001 ~ 007
 
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      "'NORTHERN STATES POWER COMPANY 00 /t   t'Il M I NNKAPOLI S.'M I NN 5 SQTA '55401 l)gf July<< 13, 1977 t
Mr J G Keppler, Director, Region       III Office of'nspection 6 Enforcement U S,Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL     60137


==Dear Mr Keppler:==
==Dear Mr Keppler:==
A k PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No.50-282 License No.DPR-42 Ino erabilit of 812 AUG'ischar e Valve The Licensee Event Report for this occurrence is reproduced on the back of this letter.Enclosed are three copies.Yours very truly, LOMay, PE Manager of Nuclear Support Services 4 LOM/LLT/deh cc:director, IE, USNRC (30)Director, MIPC, USNRC (3)G Charnoff MPCA Attn: J W Ferman, k I-over-LICENSEE EVENT REPORT CONTROL BLOCK: (PLEASE PRINT ALL REQUIRED INFDRMATIDN)
A k
LICENSEE NAME Pg M NP 1 N 1 0 7 89 14 15 LICENSE NUMBER 0-0 0 0 0 0-0 0 EVENT TYPE LCENSE TYPE 4 1 1 1 1~0 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE[oagcowr~L L 7 8 57 58 59 60 DOCKET NUMBER EVENT DATE 0 5 0-0.28 2 0 61 8 7 7 61 68 69 74 REPORT DATE~OZ EJVV~J 80 75 EVENT DESCRIPTION Jog'urin hot shutdown, while feeding the steam generators with No.12 Auxiliary 7 89 80 I Feedwater Pum'he um dischar e valve motor o erator failed.The redundant 7 89[oO~]7 8 9[oas)7 8 9 foOg 7 8 9 SYSTEM CAUSE CODE CODE-COMPONENT CODE~07~OH E'V A L V 0 P 7 8 9 10 11 12 17 CAUSE DESCRIPTION
PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282           License No. DPR-42 Ino   erabilit of   812   AUG'ischar     e Valve The Licensee Event Report     for this occurrence is reproduced on the back of this letter.     Enclosed are three copies.
~08 PRME COMPONENT SUPPUER 43 COMPONENT MANUFACTURER L 2 0 0 44 47 48 80 80 80 80 7 8 9 Qo I a random failure).Lead was repaired and valve tested for operabilit
Yours very   truly, LOMay,       PE Manager   of Nuclear Support Services 4
.80 OTHER STATUS 7 8 9[iso]7 89 FACILITY STATUS POWER~G~00 0 NA 7 8 9 10 12 13 FORM OF ACTIVE COATENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY@~2 Z Z NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE, DESCRIPTION
LOM/LLT/deh cc:director,     IE, USNRC   (30)
~13~00 0~Z NA 7 89 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION
Director,   MIPC, USNRC     (3)
~14~00 0 NA 7 89 11 12 OFFSITE CONSEQUENCES Qqg NA 7 89 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION
G Charnoff MPCA Attn: J   W Ferman, k
~1 Z NA 7 89 10 PUBLICITY NA 7 89 METHOD OF DISCOVERY 44 45 NA 44, 45 46 DISCOVERY DESCRIPTION LOCATION OF RELEASE 80 80 80 80 80 80 80 80 80 ADDITIONAL FACTORS PQB, 7 g 9~~Qgg 7 88'a A.A.Hunstad lOI~gHS~3 g0gd 80 80 PHONE.612 388-4767 ,~GPO IS1 OeT  
I
~~~y~/~4'" Event Descri tion During performance of SI 4.4.A.l, the relief valve on the discharge of standby liquid control pump 3A was observed to open at 1300 psig instead of the designed setting of 1400 psig and stuck in a partially open position.The relief valve was removed from the system, disassembled, and the plug, plug guide, and seat were replaced.The valve was tested and was observed to open at 1400 psig.It was then re-installed in the system, and SI 4.4.A.l was performed satisfactorily.
                                    -over-
All redundant systems were available.
 
A similar event occurred on this same pump on January 22, 1977, when another relief valve which was subsequently replaced, also opened prematurely.(BPRO-50 Q9$/77g)Cause Descri tion The inside surface of the plug guide and outside surface of the plug both had a scored area of approximately one-quarter inch square.The scored places caused the relief valve to stick in the open position.It is not known what caused the valve to open at a pressure lower than designed;because after the valve was removed from the system, before parts were replaced, it was tested and found to open at 1400 psig.It is possible that during the throttling process there was a pressure spike s Ij causing the valve to lift at its set pressure and stick in the open position.The scoring appears to have been caused by foreign material which worked in the small clearance between the plug and plug guide.The relief valve is a"Crosby" 1 x 2 style JMWK.Replacement parts were installed as indicated in the"Event Description".
LICENSEE EVENT REPORT CONTROL BLOCK:                                                                 (PLEASE PRINT ALL REQUIRED INFDRMATIDN)
0 mt~e t~~~4 4 tl  
LICENSEE NAME                                                                                   LCENSE                  EVENT LICENSE NUMBER                                TYPE                  TYPE Pg         M     NP       1   N     1           0   0   0       0   0   0   0   0     0       4   1   1   1     1       ~0 7 89
*O<VTIQy~'.'~as-is<~TENNESSEE YALLEY AUTHORITY CHATTANOOGA.
                  ~
TENNESSEE 37401 Zu1y 14, 1977 Mr.Norman C.Moseley, Director U.S.Nucleax'egulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., Suite 1217 Atlanta, Georgia 30303  
14      15                                            25   26                     30     31     32 REPORT       REPORT CATEGORY       TYPE     SOURCE               DOCKET NUMBER
                                                                                                                                ~OZ EVENT DATE                        REPORT DATE
[oagcowr                           L         L       0  5   0   0. 28           2       0   61     8     7   7                        EJVV~J 7   8          57      58        59        60    61                                 68     69                       74   75                      80 I
EVENT DESCRIPTION Jog'urin                 hot shutdown, while feeding the steam generators with No. 12 Auxiliary 7   89 7    89 Feedwater         Pum     'he         um   dischar     e valve motor       o erator failed.           The redundant 80 80
[oO~]
7 8 9                                                                                                                                                   80
[oas) 7 8 9 80 foOg 7 8 9                                                                     PRME                                                                          80 SYSTEM       CAUSE                                         COMPONENT            COMPONENT CODE                 -
CODE                 COMPONENT CODE             SUPPUER            MANUFACTURER
~07 ~OH                   E           'V A     L   V   0   P                         L    2    0  0 7 8 9 10                   11         12                         17       43          44                47          48 CAUSE DESCRIPTION
~08 7   8 9 7
Qo I8 9 a random         failure).           Lead was     repaired and valve tested for operabilit                         .
80 80
[iso]
7   89                                                                                                                                                 80 FACILITY                                                           METHOD OF STATUS                 POWER                 OTHER STATUS          DISCOVERY                      DISCOVERY DESCRIPTION
              ~G             ~00         0         NA 7   8         9 FORM OF 10               12 13                           44, 45          46                                                        80 ACTIVE         COATENT RELEASEO     OF RELEASE             AMOUNT OF ACTIVITY                                           LOCATION OF RELEASE
@~2             Z             Z           NA                                                NA 7   8         9               10     11                                   44      45                                                              80 PERSONNEL EXPOSURES NUMBER           TYPE,       DESCRIPTION
~13     ~00         0       ~Z           NA 7 89                   11     12     13                                                                                                             80 PERSONNEL INJURIES NUMBER           DESCRIPTION
~14     ~00         0       NA 7 89                   11   12                                                                                                                         80 OFFSITE CONSEQUENCES Qqg       NA 7   89                                                                                                                                                 80 LOSS OR DAMAGE TO FACILITY TYPE       DESCRIPTION
~1         Z           NA 7   89           10                                                                                                                                   80 PUBLICITY NA 7   89                                                                                                                                                 80 ADDITIONAL FACTORS g0gd PQB,                                                                           lOI~ gHS ~        3 7   g 9                                                                                                                                               80
        ~       ~
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                                                                                                                                  ,~         GPO IS1 OeT
 
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            '" Event Descri   tion During performance of SI       4.4.A.l, the relief valve           on the discharge     of standby liquid control     pump 3A was     observed to open at 1300 psig instead of the designed setting of       1400   psig   and stuck in     a partially   open position. The   relief   valve   was removed from       the system, disassembled,         and the plug, plug guide, and seat were replaced.               The   valve was   tested and was observed   to open at 1400 psig.           It was then   re-installed in the       system, and SI 4.4.A.l   was performed     satisfactorily.       All redundant     systems were available. A   similar event occurred         on this same pump on     January 22, 1977, when another   relief   valve which   was   subsequently replaced, also opened prematurely.   (BPRO -50 Q9$ /77g)
Cause Descri tion The inside surface of the plug guide           and outside surface of the plug both had   a scored   area of approximately one-quarter inch square.                 The scored places caused the       relief valve to stick in         the open position.
It is not known what caused the valve to open at a pressure lower than designed; because     after the valve       was removed from       the system, before parts were replaced,       it was   tested   and found   to open at     1400 psig. It is possible that during the throttling             process there was a pressure spike causing the valve to       lift at     s its Ij set pressure and stick in the open position.
The scoring appears to have been caused by foreign material which worked in the small clearance       between the plug and plug guide.             The relief   valve is a "Crosby" 1   x 2 style   JMWK. Replacement   parts were installed       as indicated in the "Event Description".
 
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TENNESSEE YALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401
    '~as-is<~
Zu1y 14, 1977 Mr. Norman C. Moseley, Director U.S. Nucleax'egulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., Suite 1217 Atlanta, Georgia 30303
 
==Dear Mr. Moseley:==
Revelatory Docket pg4 TENNESSEE VALLEY AUTHORITY      - BROWNS FERRY NUCLEAR PLANT UNIT  3 DOCKET NO. 50-296  -  FACILITY OPERATING LICENSE DPR-68  REPORTABLE OCCURRENCE REPORT BFRO-50-296/778 The enclosed report is to provide details concerning the relief valve on the discharge of standby liquid control pump 3A which was observed to open at 1300 psig instead of the designed setting of 1400 psig and which stuck in a partially open position during performance of SI 4.4.A.l. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6. This event occurred on Browns Ferry unit 3.
Vex'y truly yours, TENNESSEE VALLEY AUTHORITY H. S. Fox Director of  Power  Production Enclosure (3) cc (Enclosure):
Director (3)
Office of Management Information        and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director (40)
Office of Inspection    and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 f  (,  Qg>~
An Equal Opportunity Employer
 
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                                                      ~      LICENSEE EVENT REPORT                          ~
                          , CONTROL BLOCK:                                                                (PLEASE PAINT ALL AMUIAEOINFOAIVIATION) 1 LICENSEE                                                                                LCENSE              EVENF NAME                                    LCENSE NUMBER                                  TYPE                7YFtt Qpg        A    L    B R      F    3        0    0  0      0  0    0    0  0        0      4    1  1  1    1      0 30
                      ~
7    89                              14    15                                              85    86                        31 REPORT    REPORT CATEGORY                  SOURCE              DOCKET NUMBER                          EVENT DATE                    REPORT DATE IVD1]coNT TYPE L        L        0    5  0    0      2 9      6        0  6    2  1    7 7 7    8          57      58        59        60      61                                68    69                      74    75                      80 t
EVENT OESCRIPTION, 7
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7 8 9 89 (SEE ATTACHED) 80 80 80
    ~05 7    8 9                                                                                                                                            80 Jog                                                                                                                                                80 7    89                                                                  PRME 7
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8 9 10 SYSTEM CODE
              ~EEFF~E          EV CAUSE CODE 11        18 COMPONENT CODE A    L V    E  E 17,,
COMPONENT SUPRXA N
43          44 C
COMPONENT MANUFACTURER 7    1 0 47 N
48 CAUSE OESCRIPTION Jog                                                                                                                                                80 7 89 (SEE ATTACHED) tOOI 7    89                                                                                                                                            80
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7 89                                                                                                                                                  80 FACIUTY,                                                          METHOD OF STATUS            % POWER                  OTHER STATUS          DISCOVERY                        06COVERY DESCRIPTION E            ~OS        E                NA                    B                                  NA 7    8        9              10            18 13                          44    45      46                                                      80 FORM OF ACTIVITY      COATENT RELEASED      OF RELEASE            AMOUNT OF ACTIViTY                                            LOCATION OF RELEASE 7
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9 L~J 10      11 NA 44      45 NA 80 PERSONNEL EXPOSURES NUMBER          TYPE      DESCRIPTION
    ~SHOO                O        E                                              NA 80 7    8 9              11      18      13 PERS'ONNEL INJURIES NUMBER          DESCRIPTION
[iia]    ~oo        o                                                        NA 7    89                11    18                                                                                                                    80 OFFSITE CONSEQUENCES NA Q~g 7    89                                                                                                                                            80 LOSS OR OAMAGE TO FACILITY TYPE      DESCRIPTION NA 7    89          10                                                                                                                                80 PUBLICITY NA cn 7 8 9                                                                                                                                                80 AOOITIONAL FACTORS NA Pge 7 89~
80 NA 7    89                                                                                                                                            80 NAME:                                                                              PHONE:
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~ ', " ~  Event Descri  tion During performance of SI 4.4.A.1, the            relief valve  on the discharge  of standby  liquid control    pump 3A was    observed to open at 1300 psig instead of the designed setting of        1400  psig  and stuck in a  partially  open position. The  relief  valve  was removed from      the system, disassembled,    and the plug, plug guide, and seat were replaced.              The valve  was  tested and was observed    to open at 1400 psig.        It was  then  re-installed in the  system, and SI  4.4.A.l  was performed    satisfactorily. All redundant systems were available. A  similar event    occurred on this same pump on January 22, 1977, when another    relief  valve which    was subsequently    replaced, also opened prematurely.(BFRO 50      Q9$ /77[)
Cause  Descri tion The  inside surface of the plug guide          and out'side  surface of the plug both had    a scored area    of approximately one-quarter inch square.          The scored places caused the        relief  valve to stick in the open position.
It is  not known what caused the valve to open at a pressure lower than designed; because      after the valve    was removed from    the system, before parts were replaced,      it was    tested and found to open at 1400 psig.        It is possible that during the throttling process there              was a  pressure spike causing the valve to      lift at    its  set pressure and stick in the open position.
The  scoring appears to have been caused by foreign material which worked in the small clearance      between the plug and plug guide.          The  relief valve is  a  "Crosby"  1  x 2 style  JMMK. Replacement    parts were installed as indicated in the "Event Description".


==Dear Mr.Moseley:==
Revelatory Docket pg4 TENNESSEE VALLEY AUTHORITY-BROWNS FERRY NUCLEAR PLANT UNIT 3-DOCKET NO.50-296-FACILITY OPERATING LICENSE DPR-68-REPORTABLE OCCURRENCE REPORT BFRO-50-296/778 The enclosed report is to provide details concerning the relief valve on the discharge of standby liquid control pump 3A which was observed to open at 1300 psig instead of the designed setting of 1400 psig and which stuck in a partially open position during performance of SI 4.4.A.l.This report is submitted in accordance with Browns Ferry Technical Specifications Section 6.This event occurred on Browns Ferry unit 3.Vex'y truly yours, TENNESSEE VALLEY AUTHORITY H.S.Fox Director of Power Production Enclosure (3)cc (Enclosure):
Director (3)Office of Management Information and Program Control U.S.Nuclear Regulatory Commission Washington, D.C.20555 Director (40)Office of Inspection and Enforcement U.S.Nuclear Regulatory Commission Washington, D.C.20555 f (, Qg>~An Equal Opportunity Employer xodo)xk(f,yf)Iaaf'l) fra.".Xo',l.x"!aoiBRi.'x Ioi)g'xoSG Ju,"',,!)i XBQIc)rlui
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~+r.w 7~LICENSEE EVENT REPORT~Qpg A L 7 89 , CONTROL BLOCK: 1 LICENSEE NAME B R F 3 0 14 15 LCENSE NUMBER 0-0 0 0 0 0-0 LCENSE TYPE EVENF 7YFtt 0 4 1 1 1 1 0 85 86 30 31 (PLEASE PAINT ALL AMUIAEO INFOAIVIATION)
REPORT REPORT CATEGORY TYPE SOURCE IVD1]coNT~L L 7 8 57 58 59 60 EVENT OESCRIPTION, DOCKET NUMBER 0 5 0-0 2 9 6 68 61 EVENT DATE REPORT DATE 0 6 2 1 7 7 69 74 75 t 80[oO~]7 89 I 7 89 Qp~]7 8 9~05 7 8 9 Jog OTHER STATUS NA AOOITIONAL FACTORS Pge 7~89 7 89 7 89 SYSTEM CAUSE CODE CODE COMPONENT CODE[QQ7]~EEF F~E EV A L V E E 7 8 9 10 11 18 17,, CAUSE OESCRIPTION Jog 7 89 tOOI 7 89@co]7 89 FACIUTY, STATUS%POWER E~OS E 7 8 9 10 18 13 FORM OF ACTIVITY COATENT RELEASED OF RELEASE AMOUNT OF ACTIViTY ED>M L~J NA 7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~SHOO O E 7 8 9 11 18 13 PERS'ONNEL IN JURIES NUMBER DESCRIPTION
[iia]~oo o 7 89 11 18 OFFSITE CONSEQUENCES Q~g 7 89 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION 7 89 10 PUBLICITY cn 7 8 9 PRME COMPONENT SUPRXA N 43 44 COMPONENT MANUFACTURER C 7 1 0 (SEE ATTACHED)METHOD OF DISCOVERY B 44 45 46 44 45 NA NA NA NA NA NA NA (SEE ATTACHED)N 47 48 06COVERY DESCRIPTION NA LOCATION OF RELEASE NA 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 80 NAME: PHONE: GFO eeT~eeV t,MP~',"~Event Descri tion During performance of SI 4.4.A.1, the relief valve on the discharge of standby liquid control pump 3A was observed to open at 1300 psig instead of the designed setting of 1400 psig and stuck in a partially open position.The relief valve was removed from the system, disassembled, and the plug, plug guide, and seat were replaced.The valve was tested and was observed to open at 1400 psig.It was then re-installed in the system, and SI 4.4.A.l was performed satisfactorily.
All redundant systems were available.
A similar event occurred on this same pump on January 22, 1977, when another relief valve which was subsequently replaced, also opened prematurely.(BFRO 50 Q9$/77[)Cause Descri tion The inside surface of the plug guide and out'side surface of the plug both had a scored area of approximately one-quarter inch square.The scored places caused the relief valve to stick in the open position.It is not known what caused the valve to open at a pressure lower than designed;because after the valve was removed from the system, before parts were replaced, it was tested and found to open at 1400 psig.It is possible that during the throttling process there was a pressure spike causing the valve to lift at its set pressure and stick in the open position.The scoring appears to have been caused by foreign material which worked in the small clearance between the plug and plug guide.The relief valve is a"Crosby" 1 x 2 style JMMK.Replacement parts were installed as indicated in the"Event Description".
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Revision as of 13:48, 20 October 2019

LER 1977-008-00 for Browns Ferry Nuclear Plant, Unit 3, Relief Valve on Discharge of Standby Liquid Control Pump 3A Was Observed to Open at 1300 Psig Instead of Designed Setting of 1400 Psig & Stuck in Partially Open Position During Perform
ML18283B431
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 07/14/1977
From: Fox H
Tennessee Valley Authority
To: Moseley N
NRC/IE, NRC/RGN-II
References
LER 1977-008-00
Download: ML18283B431 (15)


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p 195 t U S, NUCLEAR REGULATORv COMMISSION NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL DOC T UMB FILE NUMBER TO:, '

FROM: DATE OF DOCUMENT Norman C. Noseley Tennessee Valley Authority 7/14/77 Chattanooga, Tenn DATE RECEIVED H. S. Fox 7/18/77 ETTER 0 OTOR IZED PROP INPUT FORM NUMBER OF COPIES RECEIVED RIG INAL UNCLASSIFIED OPY I e DESCRIPTION ENCLOSURE Licensee Event Report (50-296/77-8) on 6/21/77 concevhing the releif valve on the discharge of standby liquid control pump 3A

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y,CKZOWLEDG<D 1p++ 5p PLANT NAIIE:Browns Ferry Nuclear Plant Unit No. 3 RBT 7/19/77 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KRE~R/J. COLLINS ENGC Re~'FO FOR ACTION/I RMATIO INTERNAL D IST Rl BUTION L T EXTERNAL DISTRIBUTION CONTROL NUMBER ACRS 16 SENT AS AT 4 F a

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JUL 14 ]977 Hr. Norman C. Hoseley irector U.S. Nuclear Regul ry Comndssion Office of Inspec on and Enforcement Region II 230 Peachtre Street, NM<, Suite 1217 Atlanta, rgia 30303

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TENNESSEE VALLEY AUTHORITY - BROGANS PERRY NUCLEAR PLANT UNIT 3-DOCKET 'NO, 50-296 - PACD ITY OPERATING LICENSE DPR&8 - REPORTABLE OCCURRPNCE REPORT BPRO-50-296/778 The enclosed report is to provide details concerning the relief valve on the discharge of standby liquid control pump 3A vhich vas observed to open at 1300 psig instead of the designed setting of 1400 psig and which stuck in a partially open position during performance of SI 4.4.A.1; This report is submitted in accordance uith Brooms Fe~

Technical Specifications Section,6. This event occurred on Brovns Ferry unit 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY H. S. Pox Director of Power Production Enclosure (3) cc (Enclosure)

Director (3)

Office of Hanagement Information a d Program Control.

U.S. Nuclear Regulatory Commissio washington~ D.C. 20555 Director (40)

Office df Xnbgoqtion.~tag) gqgorceme U.S. Nuclear Regulatory Cd 'sion Washington, D.C. 20555 An Equal Opportunity Employer

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NAME LCENSE NUMBER TYPE TYF+

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"'NORTHERN STATES POWER COMPANY 00 /t t'Il M I NNKAPOLI S.'M I NN 5 SQTA '55401 l)gf July<< 13, 1977 t

Mr J G Keppler, Director, Region III Office of'nspection 6 Enforcement U S,Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr Keppler:

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PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 Ino erabilit of 812 AUG'ischar e Valve The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.

Yours very truly, LOMay, PE Manager of Nuclear Support Services 4

LOM/LLT/deh cc:director, IE, USNRC (30)

Director, MIPC, USNRC (3)

G Charnoff MPCA Attn: J W Ferman, k

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LICENSEE EVENT REPORT CONTROL BLOCK: (PLEASE PRINT ALL REQUIRED INFDRMATIDN)

LICENSEE NAME LCENSE EVENT LICENSE NUMBER TYPE TYPE Pg M NP 1 N 1 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~0 7 89

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~OZ EVENT DATE REPORT DATE

[oagcowr L L 0 5 0 0. 28 2 0 61 8 7 7 EJVV~J 7 8 57 58 59 60 61 68 69 74 75 80 I

EVENT DESCRIPTION Jog'urin hot shutdown, while feeding the steam generators with No. 12 Auxiliary 7 89 7 89 Feedwater Pum 'he um dischar e valve motor o erator failed. The redundant 80 80

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CODE COMPONENT CODE SUPPUER MANUFACTURER

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Qo I8 9 a random failure). Lead was repaired and valve tested for operabilit .

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7 89 80 FACILITY METHOD OF STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

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'" Event Descri tion During performance of SI 4.4.A.l, the relief valve on the discharge of standby liquid control pump 3A was observed to open at 1300 psig instead of the designed setting of 1400 psig and stuck in a partially open position. The relief valve was removed from the system, disassembled, and the plug, plug guide, and seat were replaced. The valve was tested and was observed to open at 1400 psig. It was then re-installed in the system, and SI 4.4.A.l was performed satisfactorily. All redundant systems were available. A similar event occurred on this same pump on January 22, 1977, when another relief valve which was subsequently replaced, also opened prematurely. (BPRO -50 Q9$ /77g)

Cause Descri tion The inside surface of the plug guide and outside surface of the plug both had a scored area of approximately one-quarter inch square. The scored places caused the relief valve to stick in the open position.

It is not known what caused the valve to open at a pressure lower than designed; because after the valve was removed from the system, before parts were replaced, it was tested and found to open at 1400 psig. It is possible that during the throttling process there was a pressure spike causing the valve to lift at s its Ij set pressure and stick in the open position.

The scoring appears to have been caused by foreign material which worked in the small clearance between the plug and plug guide. The relief valve is a "Crosby" 1 x 2 style JMWK. Replacement parts were installed as indicated in the "Event Description".

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Zu1y 14, 1977 Mr. Norman C. Moseley, Director U.S. Nucleax'egulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., Suite 1217 Atlanta, Georgia 30303

Dear Mr. Moseley:

Revelatory Docket pg4 TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PLANT UNIT 3 DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPR-68 REPORTABLE OCCURRENCE REPORT BFRO-50-296/778 The enclosed report is to provide details concerning the relief valve on the discharge of standby liquid control pump 3A which was observed to open at 1300 psig instead of the designed setting of 1400 psig and which stuck in a partially open position during performance of SI 4.4.A.l. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6. This event occurred on Browns Ferry unit 3.

Vex'y truly yours, TENNESSEE VALLEY AUTHORITY H. S. Fox Director of Power Production Enclosure (3) cc (Enclosure):

Director (3)

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

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 f (, Qg>~

An Equal Opportunity Employer

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~ ', " ~ Event Descri tion During performance of SI 4.4.A.1, the relief valve on the discharge of standby liquid control pump 3A was observed to open at 1300 psig instead of the designed setting of 1400 psig and stuck in a partially open position. The relief valve was removed from the system, disassembled, and the plug, plug guide, and seat were replaced. The valve was tested and was observed to open at 1400 psig. It was then re-installed in the system, and SI 4.4.A.l was performed satisfactorily. All redundant systems were available. A similar event occurred on this same pump on January 22, 1977, when another relief valve which was subsequently replaced, also opened prematurely.(BFRO 50 Q9$ /77[)

Cause Descri tion The inside surface of the plug guide and out'side surface of the plug both had a scored area of approximately one-quarter inch square. The scored places caused the relief valve to stick in the open position.

It is not known what caused the valve to open at a pressure lower than designed; because after the valve was removed from the system, before parts were replaced, it was tested and found to open at 1400 psig. It is possible that during the throttling process there was a pressure spike causing the valve to lift at its set pressure and stick in the open position.

The scoring appears to have been caused by foreign material which worked in the small clearance between the plug and plug guide. The relief valve is a "Crosby" 1 x 2 style JMMK. Replacement parts were installed as indicated in the "Event Description".

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