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#REDIRECT [[05000280/LER-1987-014, :on 870630,discovered That Auxiliary Feedwater (AFW) Could Be Lost to Operating Unit in Event of High Energy Line Break in Main Steam Valve House.Caused by Poor Review of AFW Supply.Review Continuing]]
| number = ML18150A497
| issue date = 07/30/1987
| title = LER 87-014-00:on 870630,discovered That Auxiliary Feedwater (AFW) Could Be Lost to Operating Unit in Event of High Energy Line Break in Main Steam Valve House.Caused by Poor Review of AFW Supply.Review continuing.W/870730 Ltr
| author name = Benson D
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name =
| addressee affiliation = NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
| docket = 05000280
| license number =
| contact person =
| document report number = 87-016, 87-16, LER-87-014, LER-87-14, NUDOCS 8708050149
| document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT
| page count = 4
}}
 
=Text=
{{#Wiki_filter:POW 28-06-_01 NRC Form 366
* U.S. NUCLEAR REGULATORY COMMISSION (9-83,)
APPROVED 0MB NO. 3160,0104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)
FACILITY NAME (1)                                                                                                                    DOCKET NUMBER (2)                              PAGE 131
* TITLE (41 Surry P9wer *station. Unit 1                                                                              !o I  5  I o Io I o 12 I 8 I O              1  loF O I 3 Inadequate R*eview of AFW Suoply FollowinQ a HELB in Safecrnards EVENT DATE (5)                        LER NUMBER (6)                      REPORT DATE (71                        OTHER FACILITIES INVOLVED (Bl MONTH      DAY        YEAR      YEAR                                                                              FACILITY NAMES                        DOCKET NUMBER(SI oI 6        31    oa      1    al 1    .:.... ol 1 14 - oI o ol 1
* 3 I o aI 1                                                                        01s1010101                    I    I OPERATING                THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR            §:  (Check one or more of the folloV(inlJ) (11)
POWER MODE (9) 1*
N        20.402(b) 20.406(1)(1 )(I)                -,__.
20.406(cl
                                                                              &0.36(c){1)
                                                                                                          ,...._
                                                                                                          ~
50,73(11(2)(ivl 50.73(11(21(v)
_,__
                                                                                                                                                          -
73.71(bl 73.71(cl
=~== : : : : :;:                                                                                          -
LEVEL                      -
1 IO I O                                                    50.38(cl(2)                          50.73(1)(2l{viil .                          OTHER (Spacify in Abstr*ct
      <101                          20.405t1H1Hm                      ,__.
60.73(11(21(11                      &0.73(1)(2)(vllll(A)
                                                                                                                                                          -    bl/ow and in T*Kt, NRC Form 366A)
                                                                        -                                  ,...._
                                                                        -      50,73(11{2){ill 50.73(11(2)(iiil            -
LICENSEE CONTACT FOR THIS LER (121 50.73(11(21(vllll(BI 50.73(1)(21(,i)
NAME                                                                                                                                                      TELEPHONE NUMBER AREA CODE D. L. Benson, Stat~n Manager
                                                                                                                                        . 81 01 4          31 51 7 I - I 31 11 8 Ill COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 CAUSE    SYSTEM      COMPONENT            MANUFAC-                                                SYSTEM        COMPONENT.          MANUFAC-TURER                                                                                    TURER I          I  I    I            I  I  I                                                I            I    I    I        I    I    I I          I I      I            I I    I                                                I            I    I    I .      I    I    I SUP~LEMENTAL REPORT EXPECTED (141                                                                              MONTH          DAY      YEAR EXPECTED SUBMISSION
:1      YES /If v**. complete EXPECTED SUBMISSION DATE)
DATE (151 nl1          ~11 RIR ABSTRACT (Limit to 1400 spaces, i.B., approximately fifteen single-space typewritten lines} (161 On June 30, 1987 with Unit One at 100% power and Unit Two at 69%
power, *it was determined as a result of a company initiated
* safety system functional inspection, that a unique scenario could exist whereby auxiliary feedwater (AFW) {EIIS-BA} could be lost to*an operating unit. In the event of a high energy line break (HELB) in the main steam valve house (MSVH) of an operating unit, the AFW pumps {EIIS-P} on that unit could be rendered inoperable due to the harsh environment. With the unaffected unit at cold shutdown and only one of its motor driven AFW pumps available for cross connect to the affected unit, an assumed loss of offsite power, with a single failure could result in a loss of AFW to the affected unit.
Administrative controls have been established to ensure that .
when a unit is above 350 degrees/450 psig, two motor driven AFW pumps will be available from the other unit.
Engineeririg is reviewing the original s~fety analysis for the HELB (loss of AFW) to assess the adequacy of the evaluation and determine if additional corrective actions are required.
97oso~o001il i~~&eo PDR          "                        PDR                                                                                                      . . . _\ t s                                                                                                                                                            P*' p., ,
NRC Form 386 19-83)
 
POW 28-06~01 NRC Form 366A*
(9-83)                                                                                                            U,S, NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION*                            APPROVED 0MB NO. 3150--0104 EXPIRES: 8/31/88 FACILITY NAME (11                                                        DOCKET NUMBER (21 LER NUMBER (61                  PAGE (31
                ?Urry Power Station, Unit 1 TEXT /ff tnOf9 _ , , . i& n,quintd, usa additional NRC Farm 366A 's/ (171 o Is Io Io I o 12 1a I o a11 - o I 114 -          oI o -o I 2  oF    o 13
: 1. 0        Description of the Event*
On June 30, 1987 with Unit One at 100% power and Unit Two at 69% power, it was determined as a result of a company initiated safety system functional inspection, that a unique scenario could exist whereby auxiliary feedwater * (AFW) {EIIS.:..BA} could be lost to an operating unit. In the event of a high energy line break (HELB) in the main steam valve house (MSVH) of an operating unit, the AFW pumps {EIIS-P} on that unit could be rendered inoperable due to the harsh environment. With the unaffected unit at cold .shutdown and only one of its motor driven AFW pumps available.*
for cross connect to the affected unit, an assumed loss of offsite power, with a single failure could result in a loss of AFW to' the affected unit.
The existing Technical Specification requires that only one motor driven AFW pump be available when the unit is at cold shutdown. This specification was developed in 1980 to provide assurance that AFW could be supplied from one unit to another in the event that the AFW pumps in one unit were destroyed by fire (Appendix R). The HELB event was not considered at that time, and Appendix R does not require cqnsideration of the single failure criterion.
This event is reportable in accordance with lOCFR
: 50. 73(a) (2) (v).
2.0          Safety Consequences and Implications This scenario is not analyzed in the UFSAR. How-ever, a main steam line break is a condition IV event and is of very low probability. Engineering is reviewing the original safety analysis to determine whether an unreviewed safety question exists.
Additionally, Functional Restoration Procedure H.l provides guidance in- the event of total loss of FW and AFW to the Steam Generators. Further protection is provided through an extensive non-destructive testing program of the main steam postulated break points in the main steam valve house .
. NRC FORM 366A (9-831
 
e                                e.pow .. 28-06-01 NRC Form 366A                                                                                            U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION                        APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31/88 FACILITY NAME (1)                                                    DOCKET NUMBER 121                                              PAGE 13)
SURRY POWER STATION, UNIT 1 o 15 Io Io Io 12 I 810 81 7 - o 11 I 4      lo In      nI  ':l OF  n  h TEXT  (If mo,e-,,.c. ia ,wqund, u* tldditioMI NRC Form 366A'1/ l17l 3.0        Cause Section l4B.5.1.7 of the UFSAR considers a HELB in the MSVH and assumes that should all three of the affected units AFW pumps become inoperable; redundancy is not lost because there are three AFW pumps* available from the unaffected unit. The UFSAR does not consider
                                    .the possibility that only one AFW pump from the unaffected unit might be available when that unit is at cold shutdown.
4.0        Immediate Corrective Action Administrative controls have been established to ensure that when a unit is above 350 degrees/450 psig, two motor driven AFW pumps will be ,. available from the other unit.
5.0        Additional Corrective Actions Engineering is reviewing the original safety analysis for the HELB (loss of AFW) to assess the adequacy of the evaluation and to qetermine if additional corrective actions are required.
6.0        Actions Taken to Prevent Recurrence None.
7.0        Similar Events None 8.0        Manufacturer/Model Number N/A NRc FOAM 366.A 19-831
* U.S.GPO: 1986*0*824-538/455
 
e
..
Vepco                                              VIRGINIA ELECTRIC AND POWER COMPANY P, D. Box 315 Surry, Virginia      23883
  . July 30, 1987 U.S. Nuclear Regulatory Commission                    Serial No:        87-016 Document Control Desk                                  Docket No:        50-280 016 Phillips Building                                                    50-281 Washington, D.C. 20555                              License No: DPR-32 DPR-37 Gentlemen:
Pursuant to Surry Power Station Technical Specifications~ Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 1 and 2.
REPORT NUMBER 87-014-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety Evaluation and Control.
Very truly yours, David L. Benson Station Manager Enclosure pc:  Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia    30323}}

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