ML18153B694
| ML18153B694 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/31/1989 |
| From: | CARTWRIGHT W R, WARREN L A VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-263, NUDOCS 8904260172 | |
| Download: ML18153B694 (21) | |
Text
,-' , e * , VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. R. CARTWRIGHT VrcE PRESIDENT NUCLEAR April 14, 1989 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 MONTHLY OPERATING REPORT Serial No.89-263 NO/RPC:vlh Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of March 1989. /$~ W. R. Cartwright Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station e e POW 34-04 VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 89-03 APPROVED:
STATION MANAGER ---------.
SECTION Operating Data Report -Unit No. 1 Operating Data Report -Unit No. 2 1 Unit Shutdowns and Power Reductions
-Unit No. 1 Unit Shutdowns and Power Reductions
-Unit No. 2 Average Daily Unit Power Level -Unit No. 1 Average Daily Unit Power Level -Unit No. 2 Summary of Operating Experience
-Unit No. 1 Summary of Operating Experience
-Unit No. 2 Facility Changes Requiring NRG Approval Facility Changes That Did Not Require NRG Approval Procedure or Method of Operation Changes Requiring NRG Approval Procedure or Method of Operation Changes that Did Not Require NRG Approval Tests and Experiments Requiring NRG Approval Tests and Experiments That Did Not Require NRC Approval Chemistry Report Fuel Handling -Unit No. 1 Fuel' Handling -Unit No. 2 Description of Periodic Test Which Were Not Completed Within the Time Limits Specified in Technical Specifications PAGE 1 2 3 4 5 6 7 7 8 9 12 13 14 15 16 17 17 18
-OPERATING STATUS 1. Unit Name: Surry Unit l 2. Reportirig Period: March 01-31, 1989 3. Licensed Thennal Power (MWt): 2441 4. Nameplate Rating (Gross MWe): --9'""4""7,...,_5-----
S. Design Electrical Rating (Net MWe): 788 6. Maximum Dependable Capacity (Gross MWe): _.;:;8.::2.=.0
__ 7. Maximum Deperidable Capacity (Net MWe): 781 e Notes PAGE 1 DOCKET No* __ s_o.._-_2
.... a .... o __ _ DATE ___ 0 __ 4.._/0 __ 4 __ / __ 8 __ 9 __ COMPLETED BY L. A. warren TELEPHONE 804-357-3184 x355 8. If Changes Occur in Capacity Ratings (Items Number 3 lllrough 7) Since Last Report, Give Reasons: 9. Power Level Io Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any: Ibis Mo!lth Yr.-to-Date
- 11. Hours In Reporting Period 744.0 2160.Q 12. Number of Hours Reactor Was Critical 0 0 13. Reactor Reserve Shutdown Hours 0 0 14. Hours Generator On-Line 0 0 15. Unit Reserve Shutdown Houra 0 16. Gross lllermal Energy Generated (MWB) 0 0 17. Gross Electrical Energy Generated
(!llll) 0 18. Net Electrical Eriergy-Generated (HWH) 0 0 19. Unit Service Factor 20. Unit Available Factor 0 0 21. Unit Capacity Factor (Using MDC Net) 0 0 22. Unit Capacity Factor (Using DER Net) 0 0 23. Unit Forced Rate 100% 100% 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each), 25. 26. Forced Maintenance Outage on 09/14/88 1 scheduled on.line date of If Shut Down At End Of Report Period Estimated Date of Startup, Units In Test Status (Prior to Commercial Operatioo):
INITIAL CRITICALllY INITIAL ELEC'!RICITY COHHERCIAL OPERA?ION Forecast Cumulative 14~6~!2.Q 88478.6 3774. 5 86605.4 3236.2 201171267.0
!2~2Q3!2ZJ.Q 61840403.0
- 60. 7% 63.3% 56.3% 55% 20: 7~ Ma~ JS ]989 Achieved (9/77) e OPERATING STATUS 1. Unit Name: Surry Unit 2 2. Reporting Period: March 01-31, 1989 3. Licensed Thermal Power (MWt): 2441 4. Nameplate Rating (Gross MWe): --9'""4=7"'"'_5-----
S. Design Electrical Rating (Net MWe): 788 6. Maximum Dependable Capacity (Gross MWe): .....;8;.:2~0;._
__ 7. Maximum Dependable Capacity (Net MWe): 781 e Notes PAGE 2 DOCRET No. __..s .... a ... -... 2 ... 0.1 ---DATE ~.a..04..:.a/_.0
.... 4,../8...,9
___ COMPLETED BY L. A. warren TELEPHONE 804-357-3184 x355 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: 9. Power Level To Which Restricted, If Any (Net MWe): 10. Reasons For Restrictions, If Any: This Month Yr.-to-Date
- u. Hours In Reporting Period 744.0 2160.0 12. Number of Hours Reactor Was Critical 0 13. Reactor Reserve Shutdown Hours 0 0 14. Hours Generator On-Line 0 0 15. Unit Reserve Shutdown Hours 0 0 16. Gross Thennal Energy Generated (MWH) 0 0 17. Gross Electrical Energy Generated (MWB) 0 0 18. Net Electrical Energy-Generated (MWH) 19. Unit Service Factor 20. Unit Available Factor 21. Unit Capacity Factor (Using MDC Net) 0 0 22. Unit Capacity Factor (Using DER Net) 0 0 23. Unit Forced Rate 0 0 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Refueling Outage on 09/10/88, scheduled on line date of June 07, 1989. 25. If Shut Down At End Of Report Period Estimated Date of Startup: 26. Units In Test Status (Prior to Commercial Operation):
Forecast INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION Cumulative 139536.0 89694.3 328.1 88293.0 0 206740436.1 67136244.0 63647378.0 6J.Ji 63.3% 58.5%
- 57.99b 15% Achieved (9/77)
-* NO. DAD a. ,. ... 89-03 03/01/89 F l F: Forced 2 S: Scheduled (9/77) PAGE 3 UNI'I SHtr.rDOWNS AND POWER REDuc.tlONS DOCICE'I No. __ s_o_-_2_8_0
______ _ UNI'I NAME _ .. s~u ... rry~_,U,_.n.,.jt..._.]
____ _ DA'IE 04/04/89 ----------------
<XltPLE'IED BY --=Laa,...:A....,,1.o.1,W1.1au
..... ~e .. n ____ _ REPOR:r HOH1'H March 1989 TELEPHONE
__ 80_4=--~35;.:7:...-.;:;3-=,l 8=-4-x3M,l5~5---
... .. C ... a o ... N 0 0
- c* C .. ... ... u .. .. 0 '1:1 .. * * :::,
- 0 .. II .. 0 : .c :::, a: :::, ::c .. .c D ... a: l 111 !i 0 C 744.0 F 1 ' Reason, A -Equipment Failure (Explain)
- B -Maintenance or 'test C -Refueling D -Regulatory Restriction LICENSEE EVEN't REPOR:r # E -Operator Training 6i License Examination F -Administrative . G -Operational Error (Explain)
H -Other (Explain) 3 .. E " C * ,n I a II C
- 0 a. 0 ~u E U PREVEN'I RECUIUlENI 0 u L 'Unit shutdown due to emergei:icy diesel generator operability concerns.
Hetboda l -Manual 2 -Manual Scram. 3 -Automatic Scram. It -Other (Explain)
,. 5 Exhibit G -Inatructiona for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) Exhibit l -Same Source -I I
- NO. D.Al'E a. >,. I-89-03 03/01/89 s 1 F: Forced 2 S: Scheduled (9/77) PAGE 4 UNl'I SHU'IDOWNS AND POWEil REDUC'J:lONS DOC1CETNO.
__ s_o_-=2_a_1~~~~~-
UN1'I NAME _ _.s .... , .. ,ccx ..... _JwZ ... o~u-... 2 ___ _ DATE _ ....... Q_.4wf0.,,,;4;i,il1.1,Rr..,9i.----~~-~
C(l(PLE'l'EI)
BY _ ... L ........ A ... e .... w .... au-... ... e ... n.__ __ _ REPOR:r HON'DI March 1989 m.EPHONE ___ 8 __ 04 ... -... 3 .. 5 ... 7-_3_1 .... 8_.4.,...xio,a,3~5...,5
___ _ ... .. C ... tll 0 .. -N 0 0
- c* C .. LICENSEE E ,r C ... ... u .... I .. .. 0 "D .. * *
- C
- 0 .. D EVENT .. "D 0 "D .. 0 : s:; :, a:
- 0 a. 0 :, ::c .. s:; REPOR:r # ~o E 0 PREVEN'I RECURREH'I D ... :I ID !; 0 0 0 -D 744.0 C 1,3 . Unit shutdown for refueling outage, automatic Reason, A -Equipment Failure (Explain)
- B -Maintenance or 'Iest C -Refueling D -Regulatory Restriction E -Operator 'Iraining 6 License Examination F -Adainistrative G -Operational Error (Explain)
H -Other (Explain) 3 reactor trip. Method: 1 -Manual 2 -Manual Scram. 3 -Automatic Scram. 4 -Other (Explain) . ,. 5 Exhibit G -Inatructiona for Preparation of Data Entry Sheets for Licensee Event Report (LEll) File (NUREG 0161) Exhibit l -Saae Source -
e e PAGE 5 AVERAGE DAILY UNIT POWER LEVEL MONTH . March 1989 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 0 2 0 3 0 4 0 5 0 6 0 7 . 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 DOCKET NO. 50-280 --,:,------:~----=---
UN IT Surry Unit 1 DATE 04/04/89 COMPLETED BY L.A. Warren TELEPHONE 804-357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77) i e PAGE 6 AVERAGE DAILY UNIT POWER LEVEL MONTH
- March 1989 DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0
- INSTRUCTIONS DAY 17 18 19 20 21 22 23 24 25 26 27 28 29 30 . 31 DOCKET NO. 50-281 --,,,---,:,-:e------
UN IT Surry Unit 2 DATE 04/04/89 COMPLETED BY L. A. *.warren TELEPHONE 804-357-3184 x355 AVERAGE DAILY POWER LEVEL (MWe-Net) 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77) e e PAGE 7
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR MARCH 1989 --------Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in significant non-load related incidents.
UNIT ONE 03/01/89 0000 03/17 /89 2144 03/18/89 0912 1302 03/31/89 1120 1234 2400 UNIT TWO 03/01/89 0000 03/31/89 2400 This reporting period begins with the unit at CSD. Loss of RHR cooling commenced due to valve mispositioning of component cooling valve by operations personnel.
RHR cooling restored -event duration was eleven hours and twenty-eight minutes. A four hour report was made to NRC for the loss of RHR cooling. Notified the State Water Control Board of significant oil leak from our underground fuel oil tank. Notified the NRC of the significant oil leak from the underground fuel oil tank due to notification to the other offsite agencies.
This reporting period ends with the unit at CSD. This reporting period begins with the unit at CSD. This reporting period ends with the unit at CSD.
e PAGE 8 F AGILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR MARCH 1989 NONE DURING THIS PERIOD PAGE 9 e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR MARCH 1989 UFSAR-88-31 CHANGE NOTIFICATION 03/02/89 l-TOP-2080 l-TOP-2081 l-TOP-2082 l-TOP-2083 2-TOP-2076 Page 9.4-33 of the UFSAR is incorrect and should be changed. No unreviewed safety question is involved, administrative correction to UFSAR only. TEMPORARY OPERATING PROCEDURES 03/03/89 The spent fuel pool cleanup ion exchanger is full of spent resin and cannot be changed out until the new spent resin transfer system is operational.
The temporary modification is to allow use of temporary*
ion exchangers for spent fuel pool water cleanup. The probability of leakage of water from the spent fuel pool is increased but the design of the system prevents lowering water level below the technical specification limit for refueling and leakage is analyzed in the UFSAR. Consequences of leakage would be loss of spent fuel
- pool cooling until water level is restored.
Testing has shown several hours before loss of cooling becomes a problem and this temporary modification would not inhibit restoration of fuel pool level. Operation of the system will be in accordance with the approved procedures;
- abnormal procedures are in effect for loss of level. TEMPORARY OPERATING PROCEDURE DEVIATION 03/03/89 03/09/89 This deviation is to ensure availability of equipment for remotely monitoring the reactor coolant system level inventory and annunciating loss of inventory.
In addition, precautions were added to help prevent PRT pressurization by not venting the unit two accumulators and requiring monitoring PR T pressure if venting the unit one accumulators.
No changes are made to the plant systems/components by this change. The change procedurally enhances the reactor coolant system inventory control and helps to ensure shutdown cooling. No increase in accident probability, consequences or results. TM-Sl-89-046 TEMPORARY MODIFICATION 03/06/89 Temporary modification to wire open the exhaust damper for l-VS-F-1 A. This change does not constitute an unreviewed safety question in that the containment air recirculation system is not required to function during design basis events.
S2-89-20 e e PAGE 10 FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR MARCH 1989 SCAFFOLDING REQUEST 03/09/89 This request erected temporary scaffolding located in the mechanical equipment room # 3 to work insulation on west wall. Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function.
Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
JUSTIFICATION FOR CONTINUED OPERATION (JCO) 03/13/89 This JCO for the emergency service water system provides various restrictions and operator actions to be performed prior to completion of various modifications.
An unreviewed safety question does not exist since the JCO provides the necessary restrictions and required operator actions to assure adequate service water inventory is maintained to keep both units in the cold shutdown condition in the event of a loss of offsite power. TEMPORARY REMOVAL OF HVAC DUCT ELBOW 03/19/89 Removal of an elbow will allow increased air flow into Unit 2 relay room and will provide increased cooling. Increased airflow will enhance the cooling in the room. SCAFFOLDING REQUEST 03/19/89 This request erected temporary scaffolding located in the # 1 emergency diesel generator room to work '1-HS-297, HS supply to 1-HS-UH-FA.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability/function.
Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
' SCAFFOLDING REQUEST 03/19/89 This request erected temporary scaffolding located in auxiliary building 47' elevation to work 1-VS-FL-3A outlet damper, l-VS-DMP-61A.
Installation of this temporary scaffolding was reviewed for effect on accident analyses and equipment operability
/function.
Conclusion is that assumptions, bases and probabilities of accident analyses and equipment malfunctions are not affected.
l-TOP-3007
Ž-Sl-89-62 e FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR MARCH 1989 PAGE 11 TEMPORARY OPERATING PROCEDURE 3/25/89 Temporary procedure to open the loop bypass motor operated valves to prevent a reactor coolant system adverse condition during reduced inventory conditions pursuant to Generic Letter 88-17. This procedure prevents a reactor coolant system adverse condition by providing a hot leg to cold leg flow path. This procedure has no negative impacts. TEMPORARY MODIFICATION Temporary modification to remove auto stop signal to containment sump pumps. .3/29/89 No safety analyses, accident or malfunction described in UFSAR is affected.
e PROCEDURE OR METHOD OF OPERATION CHANGES REQUIRING NRC APPROVAL MONTH/YEAR MARCH 1989 --------NONE DURING THIS PERIOD PAGE 12 PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR MARCH 1989 ----------
NONE DURING THIS PERIOD PAGE 13 e PAGE 14 TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL MONTH/YEAR MARCH 1989 NONE DURING THIS PERIOD _J
e PAGE 15 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR MARCH 1989 -----------
NONE DURING THIS PERIOD PRIMARY COOLANT ANALYSIS MAX. VIRGilfIA POWKI SURRY POWEi. STATION CHFXISTRY REPORT e MARCH 19 89 UNIT NO. 1 MIN. AVG. PAGE 16 UNIT NO. 2 MAX. MIN. AVG. Gross Radioact., µCi/ml l.23E-3 2.54E-4 5.22E-4 6.89E-2 9.21E-4 l.33E-2 Suspended Solids, ppm 0.0 0.0 0.0 0.0 0.0 0.0 Gross Tritium, uCi/ml ------131 Iodine , µCi/ml ------1 131 / Il33 ------Hydroaen, cc/ka ------Lithium, DDm 0. 72 0.59 0.67 0. 15 0. 11 0. 13 Boron-IO, ppm* ~20.224 409.444 ~16.241 435.707 425.908 430.502 Oxygen, (DO), ppm 1. 000 0.005 0.089 3.000 0.600 1.980 Chloride, DDm 0.011 0.006 0.009 0.024 0.004 0.008 pH@ 25 degree Celsius 5.29 5.04 5. 18 5.00 4.70 4.81 *Boron-IO*
Total Boron X 0.196 UNIT ONE: UNIT TWO: At cold shutdown for the entire month with RHR and B mixed bed in service. Excess letdown in service on 3/16 at 0030 with no flow through the mixed bed. Letdown back in service on 3/ 17 at 1830 through the end of the month. At cold shutdown for the entire month. RHR in service~ letdown out of service. 11 A" mixed bed was placed in service on 3/4 at 0545. A-MB out of service on 3/5 at 0100 as letdown was secured for MOVATS testing. Letdown in service on 3/5 at 0423, MOVATS complete.
On 3/7 at 0800, letdown out of service due to loss of inventory in the RCS. Letdown back in service on 3/9 at 2215. Letdown secured for maintenance on 3/10 at 1359; back in service on 3/11 at 0433. A-MB taken out of service on 3/15 at 2146 for PDT pumpdown, back in serviceon 3/16 at 1500, remained in service through the end of the month. ' I
,-------e e PAGE 17 UNIT 1&2 FUEL HANDLING DATE March 1989 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT I! RECEIVED PER SHIPMENT 11 II ENRICHMENT CASK ACTIVITY LEVEL NONE DUF ING THIS PJ :RIOD
- PAGE 18 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR MARCH 1989 ----------
NONE DURING THIS PERIOD