Similar Documents at Surry |
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LER-2077-009, Test of Main Steam Safety Valve Setpoint |
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| 2802077009R00 - NRC Website |
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LICENSEE NAME
@El *1 V I A I S I PI S I 2 I LICENSE NUMBER I o I o 1-1 o I o I o I o I o 1-1 ~_l_QJ 7
8 9 14 15 25 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER LICENSE TYPE l411!1l1lol 26 30 EVENT DATE EVENT TYPE lo 13 I 31 32 REPORT DATE
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B 57 58 59 60 ITT 68 69 74 75 80
EVENT DESCRIPTION
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T_h_e_c_o_r_r_e_c_t_i_v_e_a_c_t_i_o_n_t_a_k_e_n_w_a_s_t_o_r_e_s_e_t~j 7
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LI _t_h_e_v_a_l v_e_s_(_sv_-_M_s_-_2_0_1_A~, _2_0_1_B_,:...._2_0_1_c_:,:...._2_0_2_B..:,_2_0_2_c..:..)_t_h_i_s_e_v_e_n_t_i_s_r_ep=-o-r_ta_b_l_e___,p,_e_r ____ -=!1 7
8 9 80 [Qifil LI _T_e_ch_n_1._* c_a_l_S....:p_e_c_i_f_i_c_a_t_io_n_6_. 6_._2_b ___
...:(_Ro_-_s_2_-_7_7_-_0_9...:..) _________________ ~
7 8 9 PRIME 80 SYSTEM CODE
@E]!C!CI 7
8 9 10
CAUSE
CODE l!J 11 CAUSE DESCRIPTION COMPONENT CODE IV I A I LI VIE IX I 12 17 COMPONENT SUPPLIER
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43 COMPONENT MANUFACTURER I CI 5 j 6 j 71 44 47 VIOLATION LIJ 48 jolal j Five (5) Consolidated safety relief valves were found to be outside of the 3% as 7
8 9
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j found tolerance in their pop point.
The cause is attributable to normal setpoint 7
8 9 E@ I drift.
The valves were adjusted and retested satisfactorily.
7 8 9 FACILITY STATUS
% POWER OTHER STATUS EEl
~ I O I O I 01 NA 7
8 9
10 12 13 FORM OF ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY rn uJ WI NA 7
8 9
10 11 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
[Ie) I o I o I o1
~-
NA 7
8 9 11 12 13 PERS'ONNEL INJURIES NUMBER
DESCRIPTION
44 METHOD OF DISCOVERY
~J.
45 44 45 DISCOVERY DESCRIPTION I
NA 46 LOCATION OF RELEASE NA I
80 I
80 I
80 80 80 60 EE] *10 I O I 01 L___ ___
NA ______________________
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7 8 9 11 12 80 OFFSITE CONSEQUENCES
.[ili)
NA 7
8 9 80 LOSS OR DAMAGE TO FACILITY TYPE
DESCRIPTION
~~ L---::AA=---------------------------~
7 8 9 10 80 PUBLICITY
~
AA
~
L!.CJ L-------------------------------------------
80 7
8 9 ADDITIONAL FACTORS EJfil I The combined capacity of the safety valves is designed to exceed the total steam 7
B 9 80 [iliJ flow corr.esponding to the maximum steady state power that can be obtained during one, 7
89 80 NAME: ___
T_._L_._B_au_c_o_m _______________ PHONE:
(804) 357-3184 GPO BB1
e
- , ii, ADDITIONAL FACTORS (CONTINUED) two, or three loop operation, Full relief capacity would have been achieved at 1145 PSIG, 1133 PSIG, and 114Q PSIG for loops A; B, and C respectively,
- contrary to the design*.vglu.? of 1135 PSIG.
This capability would have pre-vented any overpressurization of the steam generators.
Hence, this drift of setpoint did not endanger the health and safety of the general public.
19U oc; 14 PM 12 26
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| 05000280/LER-2077-001, Re Cease of Recirculation Flow from B Boric Acid Tank | Re Cease of Recirculation Flow from B Boric Acid Tank | | | 05000280/LER-2077-002, Reportable Occurrence Relating to Boric Acid Transfer Pump | Reportable Occurrence Relating to Boric Acid Transfer Pump | | | 05000280/LER-2077-003, Submit Reportable Occurrence No. RO-S1-77-03 Re Failure of Trip Valves to Close from Control Panel | Submit Reportable Occurrence No. RO-S1-77-03 Re Failure of Trip Valves to Close from Control Panel | | | 05000280/LER-2077-004, Submit Reportable Occurrence No. RO-S1-77-04 Re Administrative Error During Power Escalation | Submit Reportable Occurrence No. RO-S1-77-04 Re Administrative Error During Power Escalation | | | 05000280/LER-2077-005, Failure of Reactor Coolant Flow Comparator to Trip | Failure of Reactor Coolant Flow Comparator to Trip | | | 05000280/LER-2077-006, No Flow of Boric Acid from the Boric Acid Transfer Pumps to the Charging Pumps | No Flow of Boric Acid from the Boric Acid Transfer Pumps to the Charging Pumps | | | 05000280/LER-2077-007, Low Boron Injection Tank and C Boric Acid Storage Tank Concentration | Low Boron Injection Tank and C Boric Acid Storage Tank Concentration | | | 05000280/LER-2077-008, Deficiency of Chemical Analysis Procedure to Determine Percent by Weight of Sodium Hydroxide in Chemical Addition Tank to RWST | Deficiency of Chemical Analysis Procedure to Determine Percent by Weight of Sodium Hydroxide in Chemical Addition Tank to RWST | | | 05000280/LER-2077-009, Test of Main Steam Safety Valve Setpoint | Test of Main Steam Safety Valve Setpoint | | | 05000280/LER-2077-010, Failure of Trip Valves to Indicated Closed on Control Room Panel, During Performance of Safety Injection System Functional Testing | Failure of Trip Valves to Indicated Closed on Control Room Panel, During Performance of Safety Injection System Functional Testing | | | 05000280/LER-2077-011, Actuation of Pressurizer Safety Valves Outside, +/- 1% Band Specified in Tech Spec | Actuation of Pressurizer Safety Valves Outside, +/- 1% Band Specified in Tech Spec | | | 05000280/LER-2077-012, Failure to Meer as Found Acceptance Criteria of Significant Number of Hydraulic Shock Suppressors | Failure to Meer as Found Acceptance Criteria of Significant Number of Hydraulic Shock Suppressors | | | 05000280/LER-2077-013-03, L Re Low Concentration of Boron Injection Tank and C Boric Acid Storage Tank | L Re Low Concentration of Boron Injection Tank and C Boric Acid Storage Tank | | | 05000280/LER-2077-013, Submit Reportable Occurrence No. RO-S1-77-13 Re Method Used to Calculate Available Net Positive Suction Head for Recirculation Spray Pump | Submit Reportable Occurrence No. RO-S1-77-13 Re Method Used to Calculate Available Net Positive Suction Head for Recirculation Spray Pump | | | 05000280/LER-2077-014-03, L for Surry Unit 2 During Normal Operation, While Attempting Routine Boration to Achieve Proper RCS Concentration, No Flow Through FCV-2113A | L for Surry Unit 2 During Normal Operation, While Attempting Routine Boration to Achieve Proper RCS Concentration, No Flow Through FCV-2113A | | | 05000280/LER-2077-014, Submit Reportable Occurrence No. RO-S1-77-14 Re Low Head Safety Injection System Will Require Operational Modification During Post-LOCA Phase | Submit Reportable Occurrence No. RO-S1-77-14 Re Low Head Safety Injection System Will Require Operational Modification During Post-LOCA Phase | | | 05000280/LER-2077-015, Submit Reportable Occurrence No. RO-S1-77-15 Re Flux Tilt in Excess of 2% | Submit Reportable Occurrence No. RO-S1-77-15 Re Flux Tilt in Excess of 2% | | | 05000280/LER-2077-016-03, T, LER 1977-016-03L Re Excessive Boron Concentration, LER 1977-017-03L, and LER 1977-018-03L | T, LER 1977-016-03L Re Excessive Boron Concentration, LER 1977-017-03L, and LER 1977-018-03L | | | 05000280/LER-2077-016, Submit Reportable Occurrence No. RO-S1-77-16 Re Unidentified Leakage During Normal Operational Surveillance | Submit Reportable Occurrence No. RO-S1-77-16 Re Unidentified Leakage During Normal Operational Surveillance | | | 05000280/LER-2077-017, Submit Reportable Occurrence No. RO-S1-77-17 Re Flux Tilt in Excess of 2% | Submit Reportable Occurrence No. RO-S1-77-17 Re Flux Tilt in Excess of 2% | | | 05000280/LER-2077-018, Submit Reportable Occurrence No. RO-S1-77-18 Re Hydraulic Shock Suppressors Found Hanging from the Wall Anchor | Submit Reportable Occurrence No. RO-S1-77-18 Re Hydraulic Shock Suppressors Found Hanging from the Wall Anchor | | | 05000280/LER-2077-019, Submit Reportable Occurrence No. RO-S1-77-19 Re More than One Snubber Inoperable | Submit Reportable Occurrence No. RO-S1-77-19 Re More than One Snubber Inoperable | | | 05000280/LER-2077-020, Submit Reportable Occurrence No. RO-S1-77-20 Re Snubber Bolts Holding Anchor Plate Had Come Loose from Wall | Submit Reportable Occurrence No. RO-S1-77-20 Re Snubber Bolts Holding Anchor Plate Had Come Loose from Wall | | | 05000280/LER-2077-020-03, L Re Failure of Valve to Close After Opening, & LER 1977-020-03L Two Containment Temperature Was Less than 100 Degrees F | L Re Failure of Valve to Close After Opening, & LER 1977-020-03L Two Containment Temperature Was Less than 100 Degrees F | | | 05000280/LER-2077-021-01, T Flooding of Valve Pit Containing Emergency Service Water Valves | T Flooding of Valve Pit Containing Emergency Service Water Valves | | | 05000280/LER-2077-022-03, L Re Routine Sampling of Bast a Revealed Tank Was at Concentration of 11.5%, & LER 1977-022-03L Re Failure of Comparator to Trip During Routine Test of a Steam Generator Level Protection Channel II | L Re Routine Sampling of Bast a Revealed Tank Was at Concentration of 11.5%, & LER 1977-022-03L Re Failure of Comparator to Trip During Routine Test of a Steam Generator Level Protection Channel II | |
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