ML18152A478
| ML18152A478 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 06/30/1988 |
| From: | Cruden D, Warren L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-466, NUDOCS 8807260416 | |
| Download: ML18152A478 (22) | |
Text
e VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT 88-06 APPROVED:.A~ Z.. l~
-stAfiON ANAGER
/
---**--*----~--- - ---- -- - -
-- -- -----~ -- -- ---..
8807260416 880630 PDR ADOCK 05000280 R
PDC POW 34-04
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 NRC Approval Facility Changes That Did Not Require NRC Approval Procedure or Method of Operation Changes that Did Not Require NRC Approval e
Procedure or Method of Operation that Did Require NRC Approval Tests and Experiments Requiring NRC 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 'l'ime Limits Specified in Technical Specifications PAGE 1
2 3
4 5
6 7
7 8
9 12 13 14 15 16 17 18 19
e e
PAGE 1
OPERATING DAU REPORT DOCKET NO.
50-280 DA?!.....,..0-7-.... 0"""7.--8'""'8 __ _
COMPLETED BY L. A. warren
_ TELEPHONE 804-357-3184 OPERATING SIATUS
- 1. Unit Name:
Surry Unit# 1 Notes
- 2. Reporting Period:
June 01 thru 30~ 1988
- 3. Licensed !hermal Power (MWt):
2441
- 4. Nameplate Rating_(Gross MWe):
847.5
- s. Design Electrical Rating (Net MWe):
788
- 6. Maximum Dependable Capacity (Gross MWe):
820
- 7. Maximum Dependable Capacity (Net MWe):
781
- s. If Changes Occur in Capacity Ratings (Items Number 3 lbrough 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
lbis Month Yr.-to-Date Cumulative ll. Hours In Reporting Period 720.0 4367.0 136079.0
- 12. Number of Hours Reactor Was Critical o~o 2312.6 87036.0
- 13. Reactor Reserve Shutdown Hours 0.0 o.o 3774.5
- 14. Hours Generator On-Line o.o 2297.6 85268.8
- 15. Unit Reserve Shutdown Hours o.o
. o. 0 3736.2
- 16. Gross !hermal Energy Generated (HWH) o.o 5322810.2 198043031.6
- 17. Gross Electrical Energy Generated (HWH) o.o 1794685.0 6416985800
- 18. Net Electrical Energy Generated (HWH) o.o 1705504.0 60860880.0
- 19. Unit Service Factor 0.0 52.6*%
. 62.7%
- 20. Unit Available Factor o.o 52.6%
65.4%
- 21. Unit Capacity Factor (Using MDC Net) o.o 50%
57.8%
- 22. Unit Capacity Factor (Using DER Net) o.o 49.6%
56;8%
- 23. Unit Forced Rate o.o 3.3%
17.3%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
INITIAL CRI?ICALI'ff INITIAL ELECTRICI'ff COMMERCIAL OPERATION Forecast Achieved
e PAGE 2
OPERATING DATA REPORI DOCKEl' NO.
50-281 DATE 07-07-88 COMPLETED BY
. L. A. Warren TELEPHONE 804-357-3184 OPERATING STATUS
- 1. Unit Name:
Surry Unit I 2 Notes 2, Reporting Period:
June O 1 thru 30, 1988
- 3. Licensed Thermal Power (MWt):
2441
---=-=-~------
4, Nameplate Rating (Gross MWe): _8
__ 4--'-7
- __ 5 _______ _
S, Design Electrical Rating (Net MWe):
788 6, Maximum Dependable Capacity (Gross MWe):
820 7,
Maximum Dependable Capacity (Net ~e):
781
- 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
- 11. Hours In Reporting Period 720.0
- 12. Number of Hours Reactor Was Critical 274.1
- 13. Reactor Reserve Shutdown Hours o.o
- 14. Hours Generator On-Line 268.4
- 15. Unit Reserve Shutdown Hours o.o
- 16. Gross Thennal Energy Generated (MWB) 627742.2 17, Gross Electrical Energy Generated (MWB) 203775.0
- 18. Net Electrical Energy Generated (MWB) 193961.0
- 19. Unit Service Factor 37.3%
- 20. Unit Available Factor 37.3%
21, Unit Capacity Factor (Using MDC Net) 34.5%
- 22. Unit Capacity Factor (Using DER Net) 34.2%
- 23. Unit Forced Rate
- 62. 7%
Yr.-to-Date 4367.0 3322.3 o.o 3288.7 o.o 7929619.4 2637535.0 2510559.0 75.3%
75.3%
73.6%
73%
24.7%
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
Refueling I Se12tember 21 1988 1 48 da~s 25, If Shut Down At End Of Report Period Estimated Date of Startup:
26, Units In Test Status (Prior to Commercial Operation):
INITIAL CRITICALiff INITIAL ELECTRICITY COHMERCIAL OPERATION Forecast Cumulative 132959.0 87988.3 328.1 86587.0 o.o 20 ~099982.1 66010359.0 62587036.0 65.1%
65.1%
60.3%
- 59. 7%'
14.8%
Achieved
II NO.
DA:IE 0...
I-88-05 04..:.09'-00 s
I 1
F: Forced 2
S:
Scheduled (9/77)
PAGE 3 UNIT SHU'rDOWNS AND POWER REDUCTIONS DOCXEt NO.
50-280
-~---------
UN It NAME sum Unit #
D............... ~07~/""'07~/~8~8...... __._ __
,U.I> -~--,,.~---------
COMPLE'J:ED BY -.;;;L~. *_A __._w.;..a_rr;.;;..;;e.;.;;n_...... __
TELEPHOW __ 8_0_4-_3_5_7-_3_1_84 ___ ~
REPORT ttJN'IH __ J_U_N_E_I_9a_a __
C
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N 0
C LICENSEE E :r C
C
... u II,n 0
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II II II C
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- I ll 0
II EVEN'.!:
.. 'C 0
'C CAUSE & CORREC'IIVE AC"rlON '.CO 0
ll
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- I Ill(
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- I ::c ll
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- 0 E
0 PREVEN'! RECURREHCE C -
Ill(
II m C
0
- E JI 0
0 C
720.0 C
1 Unit shutdown for refueling outage.
Reason:
A - Equipment Failure (Explain)
B - Maintenance or teat C - Refueling D - Regulatory Restriction E - Operator training & License Examination F
- Administrative G - Operational Error (Explain)
H
- Other (Explain) 3
- Method:
1 - Manual 2 - Manual Scram.
3* - AutOlllatic Scram.
4 - Other (Explain) 4 Exhibit *c - Instructions for Preparation of Data Entry Sheets for Licensee Event Report CLER) File (NUREG 0161) 5 -Exhibit 1 - Same Source e
-II NO.
DATE D.
I-88-07 05-16-88 F
I l
F: Forced 2
S:
Scheduled (9/77)
C DI 0
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C C
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II Ill 0
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0 UNI'I SHUIDOWNS AND POWER REDUCTIONS REPOR:r MONTH ___
JU_N_E_l_9_88 ___
LICENSEE C
E :r II,n II II C
II EVENT
.. 'O 0
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0 REPOR:r t
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0 PAGE 4 50-281 DOCKE'I NO. ------------
UNI'I NAME ---,;~~1~~~7~/Wi~~~it.-o11.#~Z--~~
DATE_...,.....,_~..,...------~
COHPLE'IED BY L *. A. Warren
'IELEPOOW ___
80_4_-_35-7_-~31~8~4-----~
CAUSE & CORREC'IIVE AC'IION 'IO PREVENt RECURRENCE e
451.6 A
3 LER-281-Unit remained shutdown for various maintenance Reason:
A - Equipment Failure (Explain)
B - Maintenance or 'Iest C - Refueling D - Regulatory Restriction 88-013 E - Operator Training & License Examination F - Administrative G - Operational Error (Explain)
H
- Other (Explain) 3 items~
Method:
l - Manual 2 - Manual Scram.
3 - Automatic Scram.
4 - Other (Explain) 4 5
Exhibit *c - InstTUCtions for Preparation of Data Ent-ry Sheets for Licensee Event Report (LER) File (NUREG 0161)
Exhibit 1 ~ Same Source e
a e
PAGE 5
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-280 UNIT --:::S:-u-rry-u=-=-n.,..,i t-#.,,.......1-DATE July 8, 1988 COMPLE'.l'ED BY L. A. warren TELEPHONE 804-357-3184 MONTH JUNE 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
'3 0
19 0
4 0
20 0
'5 0
21 0
6 0
22 0
- 7.
0 23 0
8 0
24 0
9 0
25 0
10 0
26 0
11 0
27 0
12 0
28 0
l '3 0
29 0
14 0
30 0
1 '5 0
31 16 0
INSTRUCTIONS 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)
MON'III e
PAGE 6
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-281 UNIT Sura: Unit# 2 DATE July 8, I988 COMPLETED BY L.A. Warren l'ELEPHONE 804-357-3184 JUNE 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 0
17 0
2 0
18 0
'3 0
19 147 4
0 20 492 5
0 21 753 6
0 22 748 7
0 2'3 749 8
0 24 748 9
0 25 748 10 0
26 763 11 0
27 755
- 12 0
28 766 l '3 0
29
~ 767 14 0
'30 767 15 0
'31 16 0
INSTRUCTIONS On this form.at, 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
SUMMARY
OF OPERATING EXPERIENCE MONTH/YEAR JUNE 1988 PAGE 7
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 06-01-88 0000 06-20-88 2330 06-23-88 1545 06-25-88 1608 06-30-88 2400 UNIT TWO 06-01-88 0000 0740 1232 06-03-88 1620 06-13-88 1349 06-18-88 0850 1405 06-19-88 1354 1934 2043 06-20-88 0045 1035 1812 06-2 I-88 0135 06-27-88 0100 OllO 0326 0335
- 0728 06-30-88 2400 This reporting period begins with the reactor head tensioning in progress.
RCS filled and vented.
Commenced Type 1A1 test.
Completed Type 1A1 test.
This reporting period ends with the Unit at CSD on RHR~
This reporting period begins with the Unit at CSD on RHR~
RCS> 200°F.
RCS< 200°F, cooling down due to 'A' RCP failure~
RCS mid-nozzle.
RCS filled and vented.
RCS> 200°F.
Reactor critical.
Generator on line.
Holding power at 30%, 190 MWs for chemistry~
Commenced power increase at 150 MW/hr.
Holding power at 68%, 520 MW.
Commenced power increase at 150 MW /hr.
Unit at 100% power, 790 MWs.
Declared NOUE due to exceeding two hr~ LCO on inoperable bank of control rods.
Commenced power reduction at 150 MW /hr~
Terminated NDUE holding power at 88%, 710 MWs.
Commenced power increase at 150 MW /hr.
Unit at 100% power, 800 MWs.
This reporting period ends with the Unit at 100% power; 805 MWs.
e*
F AGILITY CHANGES REQUIRING NRC APPROVAL MONTH/YEAR JUNE 1988 NONE DURING TIIlS PERIOD PAGE 8
TM Sl-88-76 TM Sl-88-77 SP-88-11 e
e PAGE9 FACIIJTY CHANGES THAT DID NOT REQUIRE NRG APPROVAL MONTH/YEAR JUNE 1988 TEMPORARY MODIFICATION 06-02-88 The primary power operated relief valves (PORVs) l-RC-PCV-1455C and l-RC-PCV-1456 were blocked open mechanically.
Technical Specification 3.1.G requires that two power operated relief valves be operable or a relief path be provided equivalent to one PORV being open.
This change will provide two relief paths through the PORVs, therefore, there is no unreviewed. safety question.
RELOAD SAFETY EVALUATION, SURRY I CYCLE 10 NP-423flR 40048 06-07-88 This report presents an evaluation which demonstrates that the redesigned Cycle 10 core and the use of the Surry improved fuel product in a core design will not adversely affect the safety of the plant during all modes of operation.
The report concluded that no changes to the Technical Specifications are required and none of the Chapter 14 UFSAR accidents require reanalysis.
Furthermore, no unreviewed safety question exist as a result of any operationai mode.
TEMPORARY MODIFICATION 06-07-88 Removed check valve internals from 1-BD-558 and installed adapter and jumper hose to condensate polishing waste neutralization or low conductivity sumps.
The steam generators will be at atmospheric pressure during implementation of this jumper. Therefore, the probability of a steam generator tube rupture is not credible. If leakage on the jumper should occur, the release can be terminated immediately by securing the recirculation and transfer pump.
Therefore, no unreviewed safety question exists.
SETPOINT CHANGE 06-08-88 The specific setpoints for the low temperature overpressure protection were changed.
Based on our review, the revision to the heatup and cooldown and the cold overpressurization setpoint does not constitute an unreviewed safety question.
The revisions restrict operations to prevent the non-ductile pressurization or over-stressing of the reactor vessel.
AC Sl-88-0608 ADMINISTRATIVE CONTROL 06-08-88 The # 1 EDG selector switch was placed from "auto" to "exercise" under Administrative Control.
Since the unit is in cold shutdown (CSD) and the #1 EDG may be started within ten minutes; if needed, the change will not affect any accident analyses or create the possibility of a new accident.
r TM S2-88-46 FS 87-53 e
PAGE 10 FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR JUNE 1988 TEMPORARY MODIFICATION 06-12-88 Removed check valve internals from* 2-BD-558 and installed adapter and jumper hose to condensate polishing waste neutralization or low conductivity sumps.
The steam generator will be at atmospheric pressure during implementation of this jumper. Therefore the probability of a steam generator tube rupture is not credible. If leakage on the jumper should occur, the release can be terminated immediately by securing the recirculation and transfer pump.
Therefore, no unreviewed safety question exists.
UFSAR CHANGE 06-14-88 Change of time delay of relays 62-AST-l and 62-AST-2 from one minute to thirty seconds.
No unreviewed safety questions exist as Nuclear Safety Analysis Group has shown that consequences of change is bounded by existing loss of RCS flow analysis in UFSAR.
AC S2-88-0614 ADMINISTRATIVE CONTROL 06-14-88 EWR-88-216 EWR-88-217 Maintained service water discharge valves 2-SW-MOV-ZOSA, B, C and D closed and under administrative control.
Since the valves (2-SW-MOV-205,A, B, C and D) remained operable and could be opened prior to auto or manual start of the recirculation spray (RS) pumps,
- the change will not affect the operation of the RS system. Therefore, no unreviewed safety question was created.
ENGINEERING WORK REQUEST 06-16-88 This engineering work request installed a blank flange on the pressurizer relief tank (PR T) aerated vents (AV) piping.
Blank flange installation will not hamper accident mitigation nor normal operation and consequently did not constitute an unreviewed safety question.
ENGINEERING WORK REQUEST 06-16-88 This engineering work request evaluated the effect of loose parts in the secondary side of Unit 2 "A" steam generator.
This condition does not constitute an unreviewed safety question because the evaluation determined that the steam generator tube integrity would be maintained and consequently the steam generator tube rupture accident results would not change.
-1
EWR-88-228 EWR-88-247 TM Sl-88-95 TM Sl-88-94 l-OP-1.1 e
PAGE i 1 FACIIJTY CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR JUNE 1988 ENGINEERING WORK REQUEST 06-16-88 This engineering work request evaluated the effect of loose parts in the secondary side of Unit 1 A, Band C steam generators.
This condition does not constitute an unreviewed safety question because the evaluation determined that the steam generator tube integrity would be maintained and consequently the steam generator tube rupture accident results would not change.
ENGINEERING WORK REQUEST 06-16-88 This engineering work request evaluated the recirculation spray (RS) system and safety injection (SI) system operability with some debris in the containment sump.
Review of unreviewed safety question indicates that use of SI/RS system components with.as-found quantities of foreign materials will. not affect safety components or system operability.
TEMPORARY MODIFICATION 06-22-88 The primary power operated relief valves (PORVs), l-RC-PCV-1455C and l-RC-PCV-1456 were mechanically blocked open.
Since the reactor coolant system will be vented through two opened PORVs, an unreviewed safety question is not created.
TEMPORARY MODIFICATION 06-22-88 This temporary modification installed a fitting and flexible hose for the transfer of ion exchange resin from l-CH-I-3A to a high integrity shipping container.
This modification did not constitute an unreviewed safety question because its probability of failure was small (due to appropriate pressure rating of components and pre-use testing of installation) and consequences of failure were previously evaluated.
OPERATING PROCEDURE 06-30-88 One of four power operated relief valves (PORV) air bottles for l-RC-PORV-1456 has a leak and is isolated. Therefore only three bottles are available.
The isolation of one of the four air bottles for back-up air to l-RC-PORV-1456 will not affect the operability of PORV. Verification that air bottle pressure is greater than I 000 PSIG will ensure that adequate back-up air is available.
Therefore no unreviewed safety question is created.
PROCEDURE OR METHOD OF OPERATION CHANGES THAT DID NOT REQUIRE NRC APPROVAL MONTH/YEAR JUNE 1988 NONE DURING TIIlS PERIOD PAGE 12
PROCEDURE OR METHOD OF OPERATION THAT DID REQUIRE NRG APPROVAL MONTH/YEAR JUNE 1988 NONE DURING TlllS PERIOD PAGE 13
e PAGE 14 TESTS AND EXPERIMENTS REQUIRING NRG APPROVAL MONTH/YEAR JUNE.1988 NONE DURING TlllS PERIOD
e PAGE 15 TESTS AND.EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL l-ST-214 2-STP-25.2A l-ST-216 MONTH/YEAR JUNE 1988 SPECIAL TEST 06-02-88 This special test was used to perform a full flow test of the inside recirculation spray (IRS) pumps by using the recirculation line installed by Design Change 88-01.
An unreviewed safety question did not exist because there was no impact on accidents or malfunctions of. equipment related to safety previously evaluated in UFSAR.
SURVEILLANCE TEST PROCEDURE 06-14-88 The test procedure monitored leakage past MOV-SW-203A, B, C & D to ensure that fouling of the recirculation spray heat exchangers does not occur.
The STP temporarily opens the SW pipe drain valves 2-SW-41 and 2-SW-54 to measure leakage past MOV-SW-203A, B, C and D and drain the piping. An operator is required to close 2-SW-41 and 2-SW-54 if MOV-SW-203A, B, C or D open. This will ensure system integrity and therefore will have no adverse effect.
SPECIAL TEST 06-24-88 This special test performed hydrostatic test of piping welds on main steam pipe (30"-SHP-3-601) and feedwater pipe (14"-WFPD-9-601) and an inspection: of welds on the 11C 11 steam generator.
The technical specifications and the UFSAR were reviewed. Manufacturer of (RV-MS-lOlC) power operated relief valve was contacted for test and design data. Possible accidents were reviewed and found to be within parameters of previously analyzed accidents.
e PRIMARY COOLANT
. ANALYSIS Gross Radioact., uCi/ml Suspended Solids, ppm Gross Tritium, uCi/ml Iodine 131, uCi/ml 1131 / 11 '31 Hydrogen, cc/kg Lithium, ppm Boron-10, ppm*
Oxygen, (DO), ppm Chloride, ppm pH@ 25 degree Celsius VIRGINIA POWER SURRY POWER STATION CHEMISTRY REPORT e
JUNE 1988 UNIT NO. 1 MAX.
MIN.
AVG.
MAX.
9.13E-2 8.46E-3 4.39E-2 2~'.89E-l o.o o.o o.o o.o N/A N/A N/A
- l. 78E-2 N/A N/A N/A l.08E-3 N/A N/A N/A 0;16 N/A N/A N/A 34.3 0.79 0.03 0.53 1.59 419. l 396.l 412-4 257-0 s.o 4.0 4.1 0 005 0.079 0.005 0 030 0.011 5.25 4.20 4.70 rl.27
- Boron-10 = Total Boron X 0~196 PAGE 16 UNIT NO. 2 MIN.
- AVG.
1~02E-2 8-9SF.-?.
o.o 0-0 4 37E-.1 1 lnF.-?.
2 ~ 56F.-4 R 9.1F.-4 0.07 0- 1 I 4.7 19_0 0 33 0-81 11 ?.
l _c;,=; 7 o.oos n_nns 0.001 in nn7 5;84 In_ 4?.
REMARKS:
UNIT I: Unit 1 was in refueling shutdown in* June; At the end at the roanth the unit was heating up (180°F) for a Hydro test. Lithium additions: 6-30 at 1955, 1560g and 6-30 at 2240, 425g for a total of 1985 grams LiOH added~
UNIT 2:
Unit 2 started the month at cold shutdown and degassed for maintenance. Reactor went critical on 6-19 at 1354, on line 6-19 at 1933 and reacbed JOO%
on 6-21 at 0500. At criticality the RCS dissolved Hydrogen concentation was only 13.5 cc/kg, less than the reguiired !Sec/kg and thereby put the unit into Action Leve) 2 On 6-2D at l055 the dissolved Hz was 15.2 cc/kg and took the unit out of Ac~ion Level 2; On 6-22 at 0830 H2 concentration was 25.6 cc/kg, thereby meeting the Admin** limit and ending Action Level 1. Lithium additions: 6-14 at 0200, 1620g; 6-18 at 0300; 1215g; 6-19 at 1410, 340g; 6-20 at 1110, 285g; 6-21 at 1515, 260g: 6-22 at 1330, 113g for a monthly tataJ addition of 3833 grams of LiOH. Cat Bed was put in service for lithium removal on 6-24 from 1215 until 6-24 at 1514 and on 6-25 from 1312 until 6-25 at 1752
- e PAGE 17 UNIT 1
FUEL HANDLING DATE TUNE 1988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT II RECEIVED PER SHIPMENT I
II ENRICHMENT CASK ACTIVITI
.LEVEL NONE DUI lING TIITS Pl :RIOD
- e.
- e.
PAGE 18 UNIT --
2 FUEL HANDLING DATE JUNE J 988 NEW OR DATE NUMBER OF NEW OR SPENT SPENT FUEL SHIPPED OR ASSEMBLIES ASSEMBLY ANSI INITIAL FUEL SHIPPING SHIPMENT II RECEIVED PER SHIPMENT II ENRICHMENT CASK ACTIVI'n LEVEL NONE DUI ING THIS P1 :RIOD
PAGE 19 DESCRIPTION OF PERIODIC TEST WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS MONTH/YEAR JUNE 1988
-~--------
NONE DURING THIS PERIOD
D.S.CBUDEN VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 15, 1988 VICE PBESIDENT-NUCLEAB 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.
NO/DAS:vlh Docket Nos.
License Nos.88-466 50-280 50-281 DPR-32 DPR-37 Enclosed is the Monthly Operating Report for Surry Power Station Units 1 and 2 for the month of June 1988.
Very truly yours, 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 4?if J *\\!