View source for HL-1492, Ro:On 910214,potential Malfunction of SRVs Suspected. Caused by Turbine Trip & Reactor Scram Valve Testing. Investigation of Malfunction Planned

{{Adams
| number = ML20091R345
| issue date = 02/15/1991
| title = Ro:On 910214,potential Malfunction of SRVs Suspected. Caused by Turbine Trip & Reactor Scram Valve Testing. Investigation of Malfunction Planned
| author name = Hairston W
| author affiliation = GEORGIA POWER CO.
| addressee name = Herdt A A
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION II)
| docket = 05000366
| license number = 
| contact person = 
| document report number = HL-1492, NUDOCS 9202050378
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT
| page count = 3
}}

=Text=
{{#Wiki_filter:_ _ --     - . . - _ . .           --
Ge. .,g g 0 3,. C m q .g ,
f           lW F' e t ~y 9 As t n a
    ,         1d tren (a wJ a 4th ter ey n;# (4 L;o :pM
           ,  m. ..; Aa w t
        ,    4,r o wm he: ; [4" t*c' P,.c 6 .s u, h i P .'e h i 12 C.
ld     ' g' i,r f is al <ir'.ct 3 ! [l                                                   ,j  ,
lea #w . '6 f.4 b Uti                                                     ,4       (,. 4 r R* P.0 A 9 :g45 1
                                                                                                  ,     g
                                                                                                             <    r . , . ,, m
,            W. G Hairston. lit i
4 w 0 e 1 n 3e: *
             !E ,K 50 d' O[ O' .t'   4 HL-149?
001235 february 15, 1991 U.S. Nuclear Regulatory Commission                                                                                   l Region 11                                                                                                            ;
A11N: Mr. Alan R. Herdt                                                                                               ,
101 Marietta Street, NW, Suite 2900                                                                                  1 Atlanta, Getmj a 30323         i PLANT HATCH - UNIT 2 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 NOTlflCATION OF SRV MAlfVNCTION

==Dear Mr. Herdt:==

Attached is a facsimile transcription of the red phone notification made earlier regarding the potential malfunction of safety relijf valves at Plant Hatch Unit 2.
We          believe this fulfills the requirements of Unit 2 Technical Specifications, Section 3.4.2.1.f.
Please contact this office if further information is required.
Sincerely, tx).k./th.-
W. G. Hairston, 111 SJB/cr Attachment c:        (See next page.)
0<i00,'.'I 9202050378 910215 PDR        ADOCK 05000366 S                                       pon                                                                      g 9-c,

    \
r (ienigial\nvel er .
l U. S. th ..W Regulatory Commission February p, 4991 Page Two c: 010f11JLfpwer Companv Mr. H. L. Sumner, General Manager - Nuclear Plant Mr. J. D. Heidt, Manager Engineering and Licensing - Hatch GO-NORMS 1).S. Nuclear Reaulatory Commission. Washinaton. D.C.
Mr. K. Jabbour, Licensing Project Manager - Hatch U.S. Nuclear Reaulatory Commission. Reaton 11 Mr. S. D. Ebneter,-Regional Administrator                                                    E Mr. L. D. Wert, Senior Resident inspector - Hatch 1
l
!                                    001235 l
l l
l

9 PLANT HATCH - UNIT TWO POTENTIAL SAFETY REllEF VALVE HALFUNCTION TRANSCRIPTION OF RED PHONE NQTIFICATION                                .
The following is an approximate transcription of the red phone notification made at 1455 CST on February 15, 1991, regarding the                        i potential malfunction of safety relief valves at Plant Hatch Unit 2.
This notification is being made in accordance with Unit 2 Technical Specification 3.4.2.1.f that requires the failure or malfunction of any safety relief valve to be reported by telephone within 24 hours of the event.
The Unit 2 reactor scrammed as a result of a turbine trip at 1854 CST on 2/14/91. During the post scram evolution, reactor pressure exceeded 1100 psig for approximately 6-7 seconds including a momentary increase to approximately 1115 to 1120 psig without a safety relief valve (SRV) lifting. Georgia Power Company has confirmed that this is well within the reactor pressure for which the vessel is analyzed; therefore, there is no safety concern. However, the Technical Specifications require the SRVs to lift at 1090 psig i i
1% (10.9 psig) for 4 valves,1100 psig 1% (11 psig).for 4 valves, and 1110 psig i 1% (11.1 psig) for 3 valves. Since no valves lifted and there are no observed parameters to support other conclusions at this time, the valves must be considered inoperable according to our Technical Specifications. The unit is proceeding to the cold                             L shutdown condition as required.
Based on these observations, plant management suspects a potential-malfunction of the SRVs. Current plans are to investigate the potential malfunction. Testing currently being performed on the-Unit 1 SRVs will assist in this evaluation. Details will be provided in the written follow-up report. This event has also been discussed with the Resident inspector and the Hatch Project Manager at NRR.-
t v
                                                                          +              w i<--           *,   ~        e}}