ML19095A367

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Monthly Operating Report for Month of April 1978
ML19095A367
Person / Time
Site: Surry  
Issue date: 05/12/1978
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: Hartfield R
Office of Nuclear Reactor Regulation
References
Serial No. 265
Download: ML19095A367 (43)
v • d • e


Text

v VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIROINIA 23261 Mr. R. A. Hartfield, Acting Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Hartfield:

May 12; 1978 Enclosed is the Monthly Operating Report for Surry Power Station, Unit Nos. 1 and 2 for the month of April 1978.

Enclosures (3 copies) cc:

Dr. Ernst Volgenau, Director (10 copies)

Office of Inspection and Enforcement Mr. James P. O'Reilly, Director (1 copy)

Office of Inspection and Enforcement

\\

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO.

78-04 APRIL, 1978 Superintendent-Station Operations APPROVED:

// 7 /~~~?;)~-

MANAGER

. r _,.

~._

I c_.

OPERATrnG DATA REPORT DOCKET NO.

50-280 DATE COMPLETED BY-TELEPHONE May J,

J 978

-~

O. J. Costello OPERA.TING STATUS

  • L Unit Name:.

Sm:ry Unit 1

  • 2. Reporting Period: o.... oo.... 1--..7_8'""0._4.:..:0;..;;l;.._...._;::2....:.4..;;;..0..;;;..0_7'-8;;..;0:...4.;...:3:...:0'------
3. Licensed Thermal Power (MWt):
4. *Nameplate Rating (Gross MWe):

S. Design Electrical Rating (Net MWe):

2441 847.5 822

6. Maximum Dependable Capacity (Gross MWe): _8'-1'"""1 _____ _
7. Maximum Dependable Capacity (Net MWe): *.,_7,,__7""-5 _____ _

804-357-3184 Notes

~ *-= *~.:-..

8. If Changes Occur in Capacity Ratings (Items Number 3 Through i) Since List Report, Give Reasons:

N/A

-~.

9. P?wer Level To Which Restricted;!! Any (Net ~fWe): _N...;./_A _____________
10. Reasoru For Restrictions, If Any: _______

.=.:N~A'-______________

. ~....

l.
  • This Month

_11. Hours In Reporting Period

12. Number Of Hours Reactor Was C~itical
13. Reactor Reserve Shutdown Hours
  • ; -14. Hours Generator On-Line
  • *
  • 15. Unit Reserve Shutdown Hours
  • 16. Gross Thermal Energy Generated (MWH) * *
17. Gross Electrical° Energy Gener.ited (MWH)°

. 1~. Net ElecrricalEnergy Generated (MWH).

19. Unit Semce f:lctor *
20. Unit A...-ailability Factor.
  • 21. Un!t Capacity Factor (Using MDC Net)
22. Unit Capacity Factor (Using DER Net)
23. Unit Forced Out:ig.e Rate 719 507 0

506.5 0

L 225,891

.... 407,570 388,075 70.4%

  • 70. 4%

69.6%

65.7%

0 Yr.-t~Date 2879 2667

  • o 2666.5 0

6,486,752 2,160,910 2,057,327 92.6%

92.6%

92. 2%

86.9%

24. Shutdowns Scheduiea Over Next 6 Months (Type. Date. and Dur:ition of E:ich ):

Hone

25. If Shut Down Ar End Of Report Period. Estimated Date of Startup:
26. Units In Test St:itus (Prior to Commerci:il Oper:ition):

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERA Tl ON 5/24/78 Forec:ist*

  • Cumulative total for Harch 1978 should have read 70,401,857

..,.f

'*' 46. -9.43-31,983.9

-~.. ' *.....()

0 71,627,748*

23,520,753 2°2,324",891 66.5%

-66. 5%

61.4%

57.9%

-16.8%

. *Achi~Yed I

OPERATli.'lG DATA REPORT DOCKET NO.

50-281 DATE 5/1/78 COMPLETED BY** O. J. Costello TELEPHONE 804-357-3184 OPERA TING STATUS

1. U;ut Name:. Surry Unit 2

.. ****2. Reporting Period:

0001

  • 780401 -

2400 780430

3. Licensed Thermal Power (MWt): __

2

...,.~... i-5-.-s---~----

4. *Nameplate Rating (Gross MWe):
5. Design Electrical Rating (Net MWe): _8_2_2 ________ _
6. Maximum Dependable C.lpacity (Gross MWe):
7. Maximum Dependable Capacity (Net MWe):
  • 81l 775 Notes
8. If Changes Occ-..ir in Capacity Rztings (Items Nwnber 3 Through 7) Since Last Report. Give Reasons:

N/A

~ :

N/A"*.

9. P?wer Level To Which Restricted;If Any (Net MWe):
10. Reasons For Restrictions, If Any: ------:----...::N.:..:./..;:;A::..._ ____________

__:.~ _ _:___:__

    • *. **.~ ;.** **
  • This Month Yr.~t~Date

_ 11. Hours In Reporting Period

. 12. Number Of Hours Reactor Was c;itical

13. Reactor Reserve Shutdown Hours

. ; *14. Hours Generator On-Line

  • *
  • 15. Unit Reserve Shutdown Hours

~*.*

719 2,879 534.5 2,376.9 0.

0.

532.7 2,373.3 0

0 1,298,587 5,774,389

  • * ' 16. Gross Thermal Energy Generated (MWH) * *.
17. Gross Electrical' Energy Gener.ited (MWH)°
  • .. "422.420 1,888,565

. l~. Net Electrical.Energy Generated (M\\VH).

19. Unit Seivice Factor 401,079 1,794,202 74.1%

82.4%

20. Unit k;ailability Factor 82.4%

.74.1%

80.4%

  • 21. Un!t Capacity Factor (Using MDC Net)
22. Unit Capacity Factor {Using DER Net}
23. Unit Forced Out:ig.e Rate 72%

67.9%

75.8%

0 0

24. Shutdowns Scheduied Over Next 6 Months (Type. Date. and Dur:l°tion of E:ich):

j" S/G Inspection;. 10-10-78, 3 Wks.

25. If Shut Down.At End Of Report Period. Estimated Date of Startup:
26. Units In Test St:itus (Prior to Commerci:il Operation):

INITIAL CRITICALITY lNITlAL ELECTRICITY COMMERCIAL OPERATlON N/A ForeC:J.st'

    • _.'.c~mclative *

. -~

28,789.7

-~-*,*-a _.:

28,302~2

. 0

..6~ '484' 623 21,455,959

  • 20,.34*7,319 64.6%

f)4. 6%

59.9%

56.5%

23.9%

Date 78-1 780422 F: Forced

  • S: Scheduled.

(l.J/77)

UNIT SHUTDOWNS AND POWER REPUCTIONS s

212.5 c

1 Reason:

A-Equipment Failure (Explain)

B-Maintenance oi Test C-Refuellng

. D-Regulatury Restriction REPORT MONTII April? 1978 Licensee*

Event Repott #

i..

  • 3 E'<t' IU IU

.... '"O Vl

(/) (.J

. (

Method:

3-Aulumatic Scram.*

4-0ther (Explain)

E-Opcrator Training & License Examination I,.

F-Adrilinistrati'le G-Operational Errur (Explain)

I I-Other (Explain) i DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEI HONE 50-280 Surry 1 May

, 1978 0, J, Costello 804-357-3184;;

y i

Cause & Conective

-Acliun lo Prevent RecOrrence Unit shutdown at end of period.

Time change 4/30/78 to Daylight Savings*

t-ime.

4 5

Exhibit G - Inst ructions for Preparation of Data.

Entry Sheets for Licensee

Exhibit I *Sam~ Smm:t I w.

I

,'.,*\\*,

L 4

"Y**

I!'! iftliiP\\if u;;;w """'4W<A 4J if I azcut

~"-

Date 78-1 780408 F; Forced

  • S: Scheduled.

('1/77)

UNIT SHUTDOWNS AND POWER REPUCI10NS REPORT MONTII ApriJ,, 1978

~L.

0 0

co...

.2 !'.?

c:'

r

'J

'I.I 0

5 *=...,

p..

l

<U i!'

-5:; ~

~ :t

~

~

11.t..c: c o--

~ Vl ~

.., o.

s 186.3 H

1 Reason:

A-Equipment Failure (Explain)

B-Maintenance or Test

('-Refueling

. D-Regulatury Restriction Licensee Event Reputt #

E-Operntor Training & License Examination F-Atlmi nist rat ive G-Operatiunal Errur (Explain)

II-Other (Explain) 3

~

Ev

<l>Vl c::

<U

-. 'OJ V>U oY u

Method:

I-Manual 2*Manual Scram.

3-Autumatic Scram.*

4-0ther (Explain)

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEl HONE 50-281 Surry 2 May I, 1978

0. J. Cos te:t"lo..,..

804-35 7-3.18~" r-Cnusc & Correclive Acliun lo Prevehl Recurrcm:e S/G Inspection -

Shutdown at start of ~

reporting period.

Time change 4/30./78 t'o Daylight Savings Time.

4 I s Exhibit G - Instructions for Preparation of Data.

Entry Sheets for Licensee Event Report (LER) File (NUREG-0161)

Exhibit I - Same Snurct I

.i::--.

I

J *

~.... ~

-~.

  • LOAD REDUCTIONS DUE TO ENVIRONNENTAL RES.CTIONS UNIT NO. 1 NONTH: APRIL, 1978 DATE TIHE HOURS LOAD, HW.

REDUCTIONS, NW RE..l\\SON NONE IURING THIS PERIOD.

HONTHLY TOTAL 0

I LOAD REDUl.ONS DUE TO ENVIRO~~fENTAL RES CT IONS UNIT NO. 2 NONTH:

APRIL, 1978 DATE I Tll1E HOURS LOAD, MW, REDUCTIONS, HW REASON NONE IURING THIS PERIOD.

NONTHLY TOTAL 0

I

:--=--

r..

DOCKET NO.

50-280 UNIT Surry 1 DATE Hay l*, 1978 COMPLETED BY O. J. Costello AVERAGE DAILY UNIT POWER LEVEL MONTH April 1978 A VERA GE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-net)

DAY (MWe-net) 1 776.0 17 766.6 2

769.2 18 765.3 3

769.l 19 765.3 4

775. 7 20 764.8 5

774.0 21 753.2 6

768.7 22 19.5 7

766.0 23 8

765.1 24 0

9 773.0 25 0

10 773.0 26 0

11 773.3 27 0

12 772.8 28 0

13 774.0 29 0

14 771.8 30 0

15 768.0 31 16 766.4 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this form, list the average daily unit" power level in MWe-net for each day in the reporting month.

Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that by using maximum dependable capacity for the net electrical rating of the unit, there may be occasions when the daily

  • average power level exceeds the l 00% line (or the restricted power level line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent ano!Ilaly.

I 1--*cc--- DOCKET NO.

50-281 UNIT Surry 2 DATE May 1, 1978 COMPLETED BY O. J. Costello AVERAGE DAILY UNIT POWER LEVEL MONTH April 1978 AVERAGE DAILY POWER LEVEL A VERA GE DAILY POWER LEVEL DAY (MWe-net)

DAY (MWe-net) 1 0

17 760.8 2

0 18 760.5 3

0 19 760.0 4

0 20 759.5 5

0 21 759.8 6

0 22 748.0 7

0 23 748.8 8

11.5 24 749.2:.

9 754.5 25 -

750.5 10.

758.7 26 746.8 11 760 0 27 749~0 12

.758. 3 28 751.0 13 760.3 29 757.8 14 760.1 30 756.0 15-759.2 31 16 760.1 DAILY UNIT POWER LEVEL FORM INSTRUCTIONS On this form, list the average daily unit" power level in MWe-net for each day in the reporting month.

Compute to the nearest whole megawatt.

These figures will be used to plot a graph for each reporting month. Note that by using maximum dependable capacity for the*net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such cases, the average daily unit power output sheet should_ be footnoted to exQlain the apparent ano_ll!aly.

r ": h1ARY OF OPERATING EXPERIENC!3e APRIL, 1978 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 1 April 1 April 4 This report begins with the unit at 100%.

At 1042 a rampdown was begun to allow repair to a boric acid v~lve required for boric acid flow path to the core.

At 1045 after= a-5 MWe-reduction the necessary repairs were-completed and the unit returned to 100%.

April 21 -

At 2150 a rampdown was started for the scheduled refueling outage.

At 2400 the unit was at 55% power.

April 22 At 0230 the output breakers were opened.

At 0255 a turbine overspeed test was satisfactorily completed.

At 0300 the reactor was shutdown.

A normal plant cooldown was commenced.

At 1500 the.unit was.< 350°/450 psig.

Refer to other sections of this report for more detailed information on maintenance work.

April 30 -

At 0200 the clocks were moved ahead 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to conform with Daylight Savings Time.

At 2400 the unit has all loops drained and head de-tensioning in progress as part of refueling outage.

There is also major primary and secon-dary maintenance underway.

During the month all spent UNIT2 fuel racks in the spent fuel pool were replaced with new

-~-

high density racks *.

April 1 This report begins with the unit in a S/G Inspection Outage.

i_-,_,_,_,,.,.--
c:::*.:c*::c:c

-..-.. oc-with.plug:*.crepa.;i_-r.:.and plugging operation in progress.

April 6 April 7 The unit heatup was commenced at 1815.

At 2040 the unit was taken> 350°/450 psig as part of normal plant startup.

April 8 At 1510 the reactor was taken critical below the Lo-Lo insertion limit.

At 1512 the reactor was manually shutdown and boron concentration corrected.

At 1635 the reactor was again taken critical and at 1820 the turbine was paralleled to the system.

At 2300 the unit was at 100% power.

April 30 -

At 0200 the clocks were moved ahead one hour to conform with Daylight Savings Time.

This report ends with the unit at 100% power.

r I AMENDMENTS T CILITY LICENSE OR TECHNICAL S IFIC.ATIONS APRIL, 1978 The Nuclear Regulatory Commission issued an order on April 17, 1978 which modifies Surry Unit No. 2 operating license.

The order results from the NRC Staff's review of the Steam Generator Repair Program. *Of signifi-cance, the order limits the operation of Surry Unit No. 2 and has the following provisions:

1.

Unit No. 2 shall be brought to the cold shutdown condition in order to perform an inspection of the steam generators within six (6) months of equivalent operation from April 7, 1978.

Nuclear Regulatory Commission approval shall be obtained before resuming power operation following this inspection.

Equivalent operation is defined as operation with the reactor coolant at or above 350°F.

2.

Reactor coolant leakage from the reactor coolant system (RCS) to the secondary system (SS) through the steam generator tubes shall be limited to 0.3 gpm per steam generator, as defined in the NRC Safety Evaluation of April 1, 1977.

With any steam gen-erator tube leakage greater than this limit the reactor shall be brought to the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Nuclear Regulatory Commission approval shall be obtained before resuming reactor operation.

3.

Reactor operation will be terminated if RCS to SS leakage which is attributable to 2 or more steam generator tubes occurs during a 20 day period.

Nuclear Regulatory Commission approval shall be obtained before resuming reactor operation.

4.

The concentration of radioiodine in the reactor coolant shall be limited to 1 µCi/gram during normal operation and to 10 µCi/gram during power transients as defined in Appendix A-1 to the Tech-nical Specifications of the license.

Appendix A-1 was issued with the April 1, 1977 Order and shall remain in effect for six (6)_equivalent months from April 7, 1978.

On March 23, 1978 the Nuclear Regulatory Commission issued Amendment Nos. 37 and 36 to the Operating License for the Surry Power Station Unit Nos. 1 and 2, respectively, which are designated as Technical Specification Change No. 49.

Of significance are the following changes:

1.

Spent fuel pool storage capacity is increased to 1044 fuel assemblies.

2.

Spent fuel cask is not to be moved into the fuel building until NRC approves drop evaluation.

r

-ll-

.Af.illND11ENTS.ACILITY LICENSE OR TECHNICAL

. ~

CIFICATIONS (CONTINUED)

On March 28, 1978 the Nuclear Regulatory Commission issued Amendment Nos. 38 and 37 to the Operating License for the Surry Power Station Unit Nos. 1 and 2, respectively, which are designated as Tech-nical Specification Change No. 50.

Of sig~ificance is the following change:

1.

Delete quarterly test requirement for main steam trip valves.

On April 4, 1978 the Nuclear Regulatory Commission issued Amendment Nos. 39 and 38 to the Operating License for the Surry Power Station Unit Nos. 1 and 2, respectively, which are designated as Tech-nical Specification Change No. 51.

Of significance is the following change:

1.

A reduction of the 6-I band to + 5% to accomodate increased steam generator tube plugging for Unit No. 2.

On April 13, 1978 the Nuclear Regulatory Commission issued Amendment Nos. 40 and 39. to the Operating Licencse for Surry Power Station Unit Nos. 1 and 2, respectively, which are designated as Tech-nical Specification Change No. 52.

Of significance are the following changes:

1.

Incorporation of miscellaneous changes submitted with proposed change No. 47 (September 27, 1976).

These changes include the following:

Exemption from monthly flow tests of engineering safety features components during extended reactor shutdown, clarification of acceptance criteria of ESF flow testing, and changing the test intervals to be consistent with the length of the fuel cycle.

2.

Upgrading of Health. Physics Supervisor qualifications.

3.

Clarification oLAxiaL Power Distribution Monitoring (APDM)

Surveillance.

4.

Deletion of requirements to measure flow rate through containment spray nozzles as part of surveillance testing.

5. __ Increase in review-time.on procedure deviation to 14 days.

FACILITY CHANGES REQUIRING A

NRC APPROVAL W

There were none during this reporting period.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL APRIL, 1978 The following facility changes were implemented during the month of April.

None of the chang~s constituted an unreviewed safety question per 10CFRS0.59.

Design Change Unit

1.

DC-77-16 High Density Spent Fuel Racks Description - This design change increases the number ~f

. storage locations in the Spent Fuel' Pool from the present number of 464 to 10_44.

This measure was necessary to main-tain the capability for full core off loa9,, and will assu_re this until 1982.

Summary of Safety Evaluation The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety and previously evaluated in the safety analysis report is not increased.

The high density spent fuel racks have been designed 1 & 2 to safely store an increased amount of fuel based on the o:i;:tg-: ___ _

inal desi*gn criteria set forth in the FSAR.

The possibility for an accident or malfunction of a dif-ferent type than any evaluated previously in the safety analysis report is not increased.

The new spent fuel racks are concept-ually the same as the old fuel racks with the exception th~t the fuel is stored in a more closely packed array.

The margin of safety as defined in the basis for any of the technical specifications is not reduced.

Conclusion No unreviewed safety question exists as defined in 10CFRS0.59.

It should be noted this design change has been i;eviewed by the NRC and has been determined acceptable as noted in the standard.review plan section 9.1.2.

Design Change

  • FACILITY CHANGES THAT

~ID NOT REQUIRE NRC APPROVAL (CON'T)

Unit

2.

DC-77-16A Spent Fuel Bridge Modification 1 & 2 Description -

The fuel bridge in.the Surry Fuel Building was analysed to verify it~ structural adequacy to withstand loadings... encountered,_.during the installation of the_ high den-sity spent fuel storage racks.

The response of the fuel bridge to static loading conditions had been evaulated by means of a linear elastic analysis using a finite element method.

The results of the static analysis indicated that the

, maximum oStresses,-,and.cdeflections.throughout the fuel bridge,~'*

members,.resulting from the applicable loads, were nominal and within allowable values.

The analysis of the welded connections between the structural members shows that the existing design at several locations was inadequate to install the spent fuel racks and reinforcement was necessary.

The spent fuel bridge was reinforced by adding gussets at 8 places and by installing additional weld metal at 4 locations.

Summary of Safety Analysis

""'.-",. The probability of the occurrence or the. consequences of an accident or malfunction of equipment important to safety and previously evaluated in the safety analysis is not increased as the fuel bridge will still be used for its originally intended purpose to move fuel.

When it is used to move the spent fuel racks they will not be moved over spent fuel.

Therefore the probability of an accident *is *not increased.*

The possibility*for an accident of a different type than any evaluated previously in the safety analysis report is not created. The fuel bridge will be used in the same manner as it is now only the spent fuel racks which can be handled will be

,,~.~ --,.. -.*..,

""'*-' *,-,_. °* ",.heavier.* nThe'"accident' an!a:lysis presented in* trhe FSAR for* fue * **"

handling accidents-will remain unchanged.

Conclusion The margin of safety as defined in the basis of any technical specification is *not reduced-. -The bridge structure is being--re- * -

inforced to ensure this.

I

' ~STS AND EXPERIMENTS REQUIRING NRC APPROVAL e

APRIL, 1978 There ~ere none during this reporting period.

ST-52 TESTS AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL APRIL, 1978 Precision Flow Determination This test was conducted on Unit #2 on 04-18-78 following the scheduled Steam Generator Evaluati.on Outage.

The test results reflected the additional steam generator plugging within the expected margin of accuracy.

Unit.

2 0~ CHANGES, TESTS AND EXPERIME~

APRIL, 1978 There were none during this reporting period.

I e --------

'*.SURRY POWER STATION I

. CHEMIS.TRY. REPORT APRIL 19 78 T.. S. 6. 6.A.11 PRIMARY COOLANT UNIT NO. 1 ANALYSIS MAXIMUM MINIMUM AVERAGE Gross Radioact., µCi/ml 3.98E-l

9. 53E-3.
  • 2.50E-l Suspended Solids, ppm
2. 4.

0.. 1 0.4 Gross f'.ritium,, µq~l~~-'--

,L69E,,-L 3 *.57E-,2-l.09E::-L Iodine-131, µCi/ml 6.61E-l 4.62E-3 5.33E-2 I-131/I-133 0.5570 0.2414 0.3585 Hy,drqgen, c.c/}tg,,,. '.

,48,0c o.o,_,. "

(1) - 28. L. **

1. 72 0.34 (1) o. 71 Boron-10, ppm +

439.2 2.4 100.2 Qx;ygen-:-.16_, _ppm, :.',., =*-

.6.. 0..

(l-o.ooo.>'.. L

-0.7'8-..

Chloride, ppm 0.13 (1 0.05 0.05 pH @ 25°C 7.90 5.34 7.18

+ Boron-10 = Total Boron x 0.196 ri, -..i.

Phosphate Sulfate 0.0 834 NON-RADIOACTIVE CHEMICAL RELEASES, POUNDS T.S. 4.13.A.8 Boron UNIT NO.

2 MAXIMUM MINIMUM '

l.40E-l

1. 97E-3 0.4 0.1 l.02E-l 2.38E-2 4.83E-4 6.56E-5 0.3312 0.0639 52.l 0.0 (2)
1. 67 0.25 (2) 303.2 91.3 2.7. (.2)-,.. 0.000 0.15 (2) 0.05 7.10 5.69 561 50% NaOH 10.50, Chlorine -~D

........... 0------

Remarks: (1)

Unit #1 Shutdown £or Refueling 04-22-78 (2)

Unit #2 Shutdown 04-01-78 to 04-05-78 AVERAGE 8.41E-2 0.2

.5-.7_6E-2.

2.89E-4 0.1064

.21,.6, 1.05 147.4

, _o,. 43.

~. ~'.

0.05 6.57

I RIPTIONS OF ALL INSTANCES WHE DISCHARGE LIMITS WERE EXCE APRIL, 1978 During this period continued maintenance was required on the Lo Level Screen and Circulating Water Pumps.

This was a result

  • of the severe icing which occurred on February.8, 1978.

Because of this ongoing _ma:i,11t~nance, _thermal discharge exc;µrsiQJJS. w~r~ _,

allowable under Techncial Specifications 4.14.B.2 while maintaining full power.

The thermal excursions were as follows:

April 9, 1978 Exceeded 15°F llT across station April 10, 1978 Exceeded 15°F.0.T across station April 11, 1978 Exceeded 15°F 6T across station April 19, 1978 Exceeded 15°F 6T across station Two of the eight screens and circulating water pumps at the Lo level remain iuoperable at the end of this report.._ ".There we}'."e no reported instances of significant adverse environmental impact.

I

J J FUEL HANDLING APRIL, 1978 No fuel was received or shipped durin~ this period.

However, all the fuel was rearranged during the completion of the Spent Fuel Pool High Density Fuel Rack Replacement Design Change.

Also, the new fuel was moved from the new fuel storage area to the spent fuel storage area, in preparation for the upcoming refueling of Unit 1.

DATE

.PPED/RECEIVEJ?

FUEL HANDLING u~HT NO. 1 P*age 19-APRIL. lq 8

.-..~~~~~~~~~~~~~

NO OF*

ASSEXBLIES PER SHIPMENT A.i.'lSI NO.

INITIAL ENRICHHENT PERIOD*

I I

r NEW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVE

FUEL HANDLING

.Page 20 U~IT NO. 2 APRIL, 19 81--~-------------

DATE

  • I NO OF IPPED/RECEIVEI?
  • ASSEMBLIES PER SHIPMENT A.i'-1SI NO.

INITIAL ENRICHMENT NEW OR SPENT FUEL SHIPPING CASK ACTIVITY LEVE

: *-...-1. '.

, NONE DU '-ING THIS PERIOD.

1.*

PRO.CEDURE REVIS IONS THAT CHANGED.E I

OPERATING MODE DESCRIBED IN THE FSAR APRIL, 1978 Th?re were none duriµg this reporting period *.

I' I

I t

-' DEScilrION OF PERIODIC TESTS WHICH w~ NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECHNICAL SPECIFICATIONS APRIL, 1978 There were none d,uring this reporting period.

, ' INSERVICE INSPECTION APRIL, 1978 As a result of the eddy current, gaging inspection in Unit #2 A, B, and C Steam Generators the following number of tubes were plugged:

A S/G B S/G C S/G 58 87 46 Westinghouse completed tube plugging on April 5, 1978.

The Low Head Safety Injection System Piping located in the Unit 1 valve pit was visually inspected.

No rejectable indications were noted.

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1.

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~'ii l/OI52' INSPECT II/IV S/!:2' TENSION/n,' flOISI' INSPSCTED + SriT 'l'BNSIONER FJOW'f 12 04/'J~/7ti 1:.'N,'/i' li11il'1l!{l;R Y!S CLEANf:V + INSE:'/JC'l'ED 1

80'1180811 1

1104190820

. --*-*nrr17577u-r
rr:p--IJmTJ!KEll 1'!*15
  • -----------~--EE:lillFJlT+TNSPE<:n*---~-"--~--~-S-04190871

(_

n11/";!i/71l Ul

!JOI' NOV-1B60/J VLl' I/((,[, NOT CLOSS ELECTRIC/ILLY

- REPLllCE'D' TORQ Si-II7'Cfl TES1' 'sll'J' 011/?7/'lb ms 1lf,/lft','./

/l-G-6 AL1lh'N DID NOT COMC:IN DURING S'l'SP ADJUS'l'ED TIMl::/1'

, --uli7
i'.17iil ___ I;'FL-rrr.r
il'KE-1,-* u-J-g-----c~L~F:-Al~J+-1~1.~1sPEC*1*

c LA'llriB'IJ+ It~sl'ec1'ED c ~7 (Jl1/'JO/'/u Ci/

l*JUV NOV-1'.381 CL'E:llfl + lll:Jl'l!X,'1'

/!EIWOI'.:.IED cNP-irfOV-115 1;; ----wi,r'fm'ilr:-

c:: ~-(~

~I i

  • 0011?41150.

1

!:104?111345 1

001111109;i) 1 801!?70745 I

~Cl

-~- *r -

1'01' /Jll il'l'M

.i

~

u 9

?4

-c, 0 0

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~~Q 48 i6 4iJ' 17

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11 20 u

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~; ~

29

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j

.JJ

  • --.**.. r.

~;.:. :.'~*_,.~

er:~ ',

~~,_)

_;_;.___c.__--"-'_;_._:..~-~"-'---.:....'----'---'-'~"--~*~*'_.::;.-"-'"-'---'-'-"----'----'-----------,---------~* I--~;

  • ,,\\I

,u JU -- ---**--**---~-----'----------------------,---=----------------'---,-------------

,II l_..u

u t.. l!>

JU - ------------*-------

11

\\.

~fj JO

  • tll
    • l
  • lb r..

47

.tu *-

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51 -- ---*-~---

w

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41

--- ~~

06 60

~~0 6-1 6>

~-----------'-~-------*----'---~~~------~------~---'--------------~--~~----~-----------*

l.* 5b

(_..

MONTHLY OPERATING SUPPLEMENT SHEET ELECTRICAL MAINTENANCE UNIT 2 APRIL, 1978

1.

MAINTENANCE ORDERS COMPLETED SAFETY RELATED ITEMS

2.

DESIGN CHANGES BEING WORKED DC-77-08, DC-76-14A, DC-74-73, DC-76-29, DC-76-10

3.

PERIODIC TEST PERFORMED PT-34 (4)

PT-23-3.

PT-23.2 PT-23.1 PT-24.SA 8

12 I w w

I

I**

C'[-

o Vl~'l-1'=/*7[,?.C

? i*iAY 7U

  • 11: ?7 A:'.!

P!IGS 1 UNIT ?-llPP.IL 1978

(:'fAillJ'6liAllCS OF SAE'l'.'TY RIJ[,IJ1'f.{) SYSTl':~fS OURING OU1'AGE 017 RB/JUC6D PO!{f!:/1' Pf,'/i.WV.J')

,l '").

li/:,'TS/;,wv1*

rs CON['

n

- ---n1rtn1-17 s-1
:1-'Cr.-ctm*

0;;

011/01/70

,r.y:

WW NOl'-?536

- 0'~/03/78 Ci/

li1' E'llL9C.~1'-'J?

--n rr/nr;17u-rr1---p;;rF7Tf;r-T-FY~u 0 ii 04/llu/7o Cl/

111' 1-Cll-P-'}0 0'1/0ti/79

/i'C VALVE.

/JCl'-7~51C.

. ;:; --otr/nr;;t11r--;r.;~r;Jf,,

('\\ ;.;

01*/07 /71l i!C MOV

/.JfJV-759?

011/07 /78 ltJ'

!JiiE'AliBli

?-/lC-l"-111

-.;; ---011J07-/70 l1T Bl1E:/J1,t:n-7=1iC='FF18 Cl;,

011/07/7tJ

,*.1*

!J/i'f','AK/::R

')-f.:C-P-1C

. iii OIJ/07/78

iS VALVI:,'

1'V-SS-?01A Df:FJ' 1'0TAL

~;'

o;;

(),,;.

':'.7 JO lt o.;;

.'.l.'l 0'"

JP - ----*---------

  • o m;sc Ii Kl-'~' Pl-'

u

.'fFt' TO'l'/Jh!f'i1'il li'TMt:l!IJI.;~ 10/nl!J/'. + 715.. n C/lr.C1\\W t1Gll1'NC..56-NV P/10/Jf,llMS 7-il"CT10"91JUS U

DISC/RECO<'J,V E'Oli' 'Jf.CllS DI8C//1'/;;c+n*sn11

?

00*3:nn:30 105

1 'J w:1 AL11!1N '}-Cl/-'311'}

NO r1;013u~*n l"OIJNJJ

?

BOUO?i?IJl.I 71 ClltlNezb (JlJ, 17il,ED OlL+Tt*l~l*£t1(,1;D/JT::iffinva-------:-7-irn109:t'J55'_'_]5T ___________________,,,

ltb',1T 'l'llACDJG /II!il\\ RRO/(l.;f{

lt'Bl'Lt1CB1J /JEAT/f,'115

?

UOIHJ3?3;i?

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AD..JUS1' [,f:\\IIJ'S ATJJIJS1'/S!J + fl','S1.'IW

7.

ao111JIHJU05 5?

t-l!..1tS/lflTCTJc;Ti1r.,~1r~n~,1~1*~c~R-A~1r,;~11~(1~.1 "1~,v,.----1~,*E~,z~,,IJ~AC'IJ7T'T7Tl1' 511'11'CH 11/IN.

  • ----,'---imrios1n"?s----,,~ ------------*-,,

LINIT S'i-IITC!I GUI/JB OUT OF GUJD8

  • Rl':l'LtlCED GUIDS /JO/.,TS *

'?.

OOUOG.1900 13

~'}
  • Clil~C.r<. mn.~Y SfiTUNGS RE-1.'i:,'ST.'SJJ 0 P/JIJSI:: f11'J[,AJ '

' '}

80llOG;>3:30 D

~**

  • '" -1'E:ST1SUiJ P1w:,1; 11t.L7T.I

-"-7--:1rnnuu7Tn-----*1r----------*------*--- ;,

C:1LCll itSCAlSrrrT,,,

C/if,'Ck. lt'/S/.,Al' Sf.'l"fINGS POSl'fION I/WICATIOll CIROl/G

.~ 1;. ' *.

TES7.'l!W D P/JASf,' li6'LAY ONL-Y.

?

801106?3'3?

17.

IIEPDACtD+St:T Lil-!1'7' S11LTC/J

  • 7.

8011070B'30 3

I) in')

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_____________ : "" f

.! )

i:,:1..

  • ~~ ~')

'-----*- ~;1 *

,\\*j

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  • ----~----}~o

' ' ------*-*.. --,---. ;;b

**-~:.b 6t10 J_:

~J~

  • G

~l 0 *~

-* --_--(.:_ ________ _,.-----------------------"-----------------*---------~

0 ~"

!--~----.. -- -*-----*

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() ~~ #

1nkJ i\\ ~i

  • ---* i~l n

t 7 ---~-*-*~-~----- --****----*~ *---.. -*--*---*------**-~--* ___________

.. ~---~-----*-------------h*-**-**-** -*----*--*--*--**-----*---*--*-*--------*-------*--*-- ;~

1.
3.

MONTHLY OPERATING SUPPLEMENT SHEET INSTRUMENT MAINTENANCE UNIT 2 APRIL, 1978 MAINTENANCE ORDERS COMPLETED SAFETY RELATED ITEMS PERIODIC TEST PERFORMED 8

59 I

LU Vl I

.,,--U-F.:-l*-T--=I-.~-,S-1-' -----------*--------------------------------------*-')-/-IA~~~-*-1~?-7-11.-

1 1-l'AGl:~----------,--~l O

>.*----------------------~----------------------~-------------------------------0--- ;'

l., 2 Ul/17' 'J.-Al'l1Ilr 1970

  • ~

f :i lNAil/1'b'NA!ICF.: OF SAFIST'i [i[o;[,/i'f.5'D SYS1'/;;rJ/j DURING OUTAGE OR l/EIJUCED po;nu l'S/\\lODS)

*r -
  • libTSGl:VD;"

SYS CO' fl' NA/i'KNO

-DESC lvliPI>lit' u

.Jfi T01'1NtV1'N 6

1 Glfi0117 n-t:~r:.r*r,.,C'"'T""O""J,,.., --t[)"r-------n11t1TO I.1Sc111 lr01iHJ/vG TIOrli11, h6f"Cll.Cl!:TTEiVCODB11 +.liODl FTETl-VTiiIIVCr 7

701773SO----,~~~

01*/ll3/7B*

cc ING1' n-CC-7078

.* ERf1A1'IC f'W!v INDICA1'ION IN CONT *m.(.. fiEl;&/JC{:)D TfiANSr'ID"rnR 9

011/0S/71J C/J VALVE llCV-')111 DOSS NO'l' /1'[*.'GUD/Jtf; l!'LOlv l'ROL'ERL'I CLEAN'f.,'D OUT CLOGGJ:,'V /JLR UNI!:

7 8011316U5 173U 807070971 117

-.; --0117n
;17s--u1:rc--.1i.,.t-""1---..,v.,,.u.,,.t1..------.ll~*1""',.""".J"'Ji'E-1..-,"'n.....

11,...,C""l""11..,'l"'u,,.1,......,.C.,.,1J'"'V'"'ul"'1C,.,.'ll,,...,...

s)..--~~-.,...,.;,..L,,..:~1"'1/.,.1'C...,u*"w""l""ll,,..,,..,./'"'&.-.,.11n11no~1":*T1c:r:IT.TFSllT----r-uo:non1n--r.rsir-

.... ii 0'1/IJ5/7Jl Cl/

INST

/iCV-7185 DOCS NOT CONllOL PllOP/;R[,'i RIWUcr:;o SP.tl'tl/IG MR ['l\\/SSSU/il\\S 2

8033110/0

/5 OU/05/78 li'!I CONT 7-Rll-')758 AIR r.::,;U[,fl'J'OR DI/Jl'/IR/J,lf L!S/J/(S RE'PLACB'D uo PSI m:GULA'l'OR uo:n11uoo n

~tJS171l-Vll"----,lnN~b~1'..---t~1~-~1~1~.'2n11r-----1r.cE~11~vm5,.-.,qrr()~G~F~
1rr.r117 1~1*~n-1uvun-;m1c~1~*on;n11--i
E~lJJ'Tn:lN--.-~znL~*1~1onb~u.-..~T</1~1~1'1~*~~*1~,*~u7~

1m10TI&~1<r-r1-~1im*ll~sTS--*--,--~~,. -uanITUJ7U0'2 7u*--------------

    • ;~

OU/05/78

/IC V/Jl,VE llCV-7:?01 SlROli.l:l VALVE AND SE:T UP AIR P.RF.SSURE.'

BLT::CTI/ICAL DBP! SET LINIT.SWI1'Cf/ES

?

80U0373tt5

?U 16 -V:'W.JT07'1t~

u700

"'\\ i7 21,. ---------------------~--'----------~-----~---------------------------------*---------*----*

\\...

I w

)

In -)

II I~

1.1...

l'i 1*;

11

'" )

  • 11

.I'

*-------------------------~------'-'--~---'~~"'-----------------------------------... ------

°'

1r-,

I.. II

.::: ')

1--------------------------'---"---'---"--------------"------------------------------------**----**

.1**.)

~~; *.~)

.1!l

.m

.UJ

~-----------------------------------------*-*---*-**-----*-** ---***-**--*-----*--- **-***

~*-*

,,:\\------------------------------~-----------------------------~------~-----*--------*-------~*,

() ~.;

(..., --

../ *~~

!1~

c..;;,-;

  • ll_.-...,,

.;!-t *. :*.:

r;o

---*----*--*-*---------------~----- ------ Oi r.n

***-----------------~--------------* - i,O

~o
  • ---------------- -----~------------~----------~------------ --------**---**---- -----------------------------------*--

72

~-7 ------*-**--*-------*------------.*.,..

(.:..,.

'"1 "

/t;

~---~---~--------~--~---------~/

I l'

~ REP_ORT OF RAlH.OACTIV~ EFFLUENTS I

Fndl.lty:: Surry Power StntJon Jotk1n:

'50-21:\\0 nnd 5:0-281

  • j I.

LT.QUill HELE/\\SES *

.. -===-====~=="=-=====~:=-=>====*==~~=:-==o=z===========-,,,,..,,,==--=-==r=x===:c:i:==-=====.-r=-=I 4-L-~-===z=::::=~ll==-==========F===========w=~l===========:=:~r:c========c:=lt====o=======ir-==<====-=--==I

*-------*-----'--------------J1 _._u_N_r_rs_-l1--"'J~f'!.u.NU><..!A'°"R"'"'Y..__" _

_,F~*

E:..,.n,_,_,rr~uAR:..:..Y=---11---=*i:.=.1J\\=R=c~a'----ll--'A'"'"'P'-'-R.,,.,1....,1,___ __

H... *------ll----~

I,

(:ros~; R<JclJ onctJ.vity WY)

*--(...::n....;.).::;.... ~-='I.:.:.'

o:..l:.:..::..a.:l_ :.....:l:.....:\\e'-1-~-a~s c'-*. -'"---'--'--...;.._---- i1--i:;-u-r...,..i_e. s-:~==6~~::1::2 E:, -:1:::==~~==5 :.1:L=1 c:=, -=2===:Hf=:l.!=:. *:7 o:E:*-:2:===:::=::1 =* 6:::3:E:::-:1:==~::=========~-l 1

~---_ ---_ ---_ ---_ --1-1

~-~)1 Avg. Concentration Released

µCi/~1

-~2~:3~4~E~-£9-~-~2~~~4.:..:.l~E-.;....:1.::;...*0~*-1~2-._1_7_E-_l_0_~~~6~*~8~6~E-~1~0~~~~*-*-~-~~--~

(c)~

Maximum Concentration Rcleasetl

]JCi/ml

_5~~1~4~E~-~9-~--*3_~_4_7~E-_l_n_*~

1~2~._7_1_E-_l_0~-~~5~,~6~7E~*-~1~0~~~----~-~~---~

2.

Tritium (n)

Total Released Curies

9. 27E+l 2.35£+1 5.l2B-/

(h)

Avg. Concentration Relensed pCi/ml 3.54E-7

1. J.OE-7 8.i3E+l 3.43E-7 39 Dlsso.lvecl Noble Cases (n),

To tu l Release Cur:les 2.38E-1 l.lflE+O 3.67E-1 9.97E-l (b)

A '!J2., Concentrnti.on Released i1Ci/ml 9~08E-10

5. 55E-9.
1. 69E-9 4.21E-9 Gross t\\Jplli:1 Racllonctivity (n).

Totnl Relensed

i. 86E-6 (Ii)

Avg. Concentration Ifolensed pCi/ml 4.43E-14 8.SSE....:15 8-lOE-llt

?_.:... __

~ol. of L:l.quid to Disch. Cnirnl Liters

3. 371!.+7 7,.17E+7
3. 39E+7 2-8'H'+i
6.

yoL. of Dilution Wnter Liters 2.62E+ll 2.13E+ll 2.17E+ll 2-37E+ll

7.

Tso tones Released MPC µCi/ml Curies T-131 J x 10-*i l.l12E-2 8.96E-3 1.02E-2 2.0BE-2

.--------lf-----11-..:::..:....:.=::-'---11*-=-~=:....-=--~-~;;..,=.;:;__;;:'---11--'::-:.....::~'-=---lr~------11---~--;

l-132 B x 10- 6

1. 71E-l1 Q.96E-l1.

4.20E-2 5.49E-4 1-133 l x 10- 6 3.72E-4 6.06H-4 4.39E-2 5 07E-1 I-lJ/1 2 x 10- :i 5.15E...;L1 5, 33E-4

4. 20E-2

. T-lJ 5

/1 x 10::.l>*--------H-----u--l-.-o-3~8E-,--.4,--

11-6-.

7-0-E~--4--

11,_5.=-.1~9;:.c;E._* -_;:;2'---*ll-5-.-l-6-E---4--11-------n------1

cs:l.)t1 9 x 10-=-ri-1.73E-2 2.22E-'2 i.76E-2 1.14E-2 Gs-.136 6 x io-~

l.35E-3.

9.27E-5 7c

-- 'Cs-137 2 x 10-:i J.39E-2 L1.65E-2 3.82E-2 C~;-1.JB Z:~ 22E-4

~

1. 86E-2
1. Sl1E-4
1. 56E-4
1. 64E-3 1,. ll1E-l 2', 54E-Z.

L OJE-1 Co-57 t, X* 10-'1*

C-o-5B 9 x io- ~

11-....,.--,

J... 0 3 E-1 6. D GE-2 8

  • 13 E-2
  • ----Co-GO 3 x io- ~

r:1~1-sii 1 x 10-11 6*. 94E-3

2. l13E-3
5. 2J.E-3

,------11----

1.. 5 9 E-2 2

  • 511 E-2 5
  • 5.lE-1 Nn-211 3 x 10- 5 Cr..!51 2 x 10- 3 3 ~ 60E-2 6.161?.r-3
3. 32E-2

---i1

'F-c-.19 5 x J.Q-5 9:,Q9E-L1 1.51E-l1

'l.06E-4

--:-Nb-95 l x f0- 11 3:, 51E-3 El. 31,"fr-t,

3. OlE-3 2.14E-2 l.33E-4
1. 40E-l 9.19E-2
9. 51E-3 4.70E-4 3.97E-2 3.33E-3

--.-.. l~.:i-1:7\\-.J/10 2 x 10-s 1.81E-3 7.113E-l1 9.25E-5 II

*-----"-------11-----11--

ll~~~-=----11-*-------11----~-~11-----~

U=.~ **=}~b-~41f--=~-------

_____

  • ____ _,,_ __ l.36E-3 2.lOE-3

\\,.,

I I

v

  • 1*

\\

Fl\\CT.l.lTY: '-'*11~~wcr Sl:n~~~--..

.1.

I I..

LlQll,ID RELEASES (CON 1 T) xe:..],)J J X 10-U

~

2.orn-1**

I l.OOE-1

! 3."08E-1""

i! 9.49B..:1 f 3'.62E-2

.I 2.0SE-2.

. 1 3.24E-2 i, 2.91E-2

..___""""'-"--~---ll*------->>---~----'

3.!31E-5..

  • 91.JlE-6*

.. ~e

  • "le" C-ll1

!3 x i)_o-11

~-*,9, Percent of 10CFR20 l~lOE~l 1:72E-l

... --.----n--~-=,,,r.=---11--'----"'"'-.-.

~...:..: ------11------

5:J.,9E-2

3. 71E-2 Percent
11.

AlRBO!l.NE RELEL\\sgs L_._

Total Noble Gases Cur:les 9~47E+l*

L1.BOJH2 '**

  • f.9.St:+z*
  • L"2"4.E+"3 J_'.---.~~~n l_)_la ~s:g'-c_n_s ____________

11 Curies

--l-.-2...,_3_E __..,..4--u--,2.-*..,,9~o=E--~ 736E-4___

5. 34E-3

'..I.

To t---lll------ll..,..------11-----~

(1.

Mnx:im1.1111 Noble GCls Re.lense Rate JJC1/sec

*-----------11-----11-----'--'---'-_,_,_*ll--.u_---'~-~ll~_.._--"~---H------

--,-~---1~----~

7.

Percent of Applicable Limit *for

__,_,'l'ccl111J.cal ~ed(J.cations

{~)

Nob.le Gases (b) lln.logens Percent '

I Percent **

---(c)

Parl:iculates Per.cent

  • 1 B.

Isotopes Released:

Curies (a)

Pa1*tlc111at.:es

-*-----'-~-----------------11-----1~------H------.ll---'-----11-------11-------1~---~-

Cs-.lJ 4 2.0liE-5 9.5(1E-7 7.20E-9

~-r.-.s-135 i- *

,*e

-le Cs-13 7 l.53E-8

l. lt 2E-6

__L_l!l.... E-_6,,__

111_-'-"l"""". ""-J 7'-E-~--"6 __

11 ______

11 _____

~

C:O;-J JB 2.17E-3

_J~;,::).____

11 ___

  • ___

11 _____

11 ____

________ "_---~'.Q::28 J *. OSE-5

2. 60E-6

_l.._JJ_,F_-_'i__,,_"'"-7_. 9~7_E_*-~5 __

11 111 ______

(, r.o 5.21E-5 J "J6E 5

  • 11t*J~*-"1 4.87E*-6

--*----~-..:Q..:\\1

__.!..L.~-'-""'---11

___ _:*--"-----~---!_1~1-:_)~!________

J;JliE-'6 5.'75E-9

,*e 11 _' ______

11 _____

I F1~-5<J I

-~~=-~, ~-:-~=-~-~i?~~:ttn -~-~~~"=-=~"='-=='=-~--==.... *---=-~~ ~--~-~~-=== ;r=~~~.,.~~-s -"""'.:-_];. *.. 2 7E-s.=11 -=-.w-._.

-.im=_1_=-t_1=-_ -.. =:<-11111*---*---,,-",rr=""""'.-_-~--.=:

,---.... =---===

  • 1 Ji.'*-........-

I

,\\.

'(

11_.~

,I 1*,; ',.

I

_.,,, **..,..,,,.,...,, **** <... o. *** :L.~**'*,::1-:...;,..

IJ.

ArnnORNE RELEASES (CON'T)

' 1 I

  • i1 UNITS.

JANUARY FEilRUARY I

~'.ITt="*:~c~f.E"2'l:c;~;~9=rrc;1_,~;;c1(~on tt)==="=====*

11=curie-s 111=~

~1.=====

.. "":="", """".,===<<~======.=;,==,;,c,.,=,,,

1'-=-======"

11"'"="'==========~

1====-===*

11==========----=-

( b) llnlogens I

\\

~------I_-_l_JJ_. __________________ ~r----~',,, __ 7_~.*~*3~9~-q_,~__J,.. _7~.i~-E~-~5--~11--"'-'-~"'"-.___,11~-----------if-----~-~~i~-----~

l-.132 r

i;_;ot,~n,,)\\;_,-

~.

~---~--~---11----:----;*11-~

1-133 2; 1 Sg-6,

l. 81E-6 I-1Jl1 11--------,.,..--I-l 35 Xc-133m Xe-135 Kr-!37

Kr-88 J\\r-l1 l SOLID R.l\\DIOJ\\CTIVE WASTE DISPOSAL UT..

l.

(a)

Total Amount Solid Waste

~-----------l'c_ac_*\\_(u~g~e_<l_. __________________ 11 __ F_T_3 __

  • ~~,---60,__f_t_._

3

_:_* __ 11 __ 7_._7_6_E_+_2 __ ~

11~-7~._2_lE_~*+_;z_*_*_* --1i-~2~**~*1~2~E~+~3--~~-..,.-----~---tt----~-

(b)

Estimated Total Activity Curies 1'.625 1.12E+l 9.20E+l

  • 1.'32E+2 (c)

Date of Shipment and Ilarnwell, Ilarnwe~l~....

Barni;;,ell, Ilarnwell,

~* I...

DJsposi~ion S.C.

S.c*.*

S.C.

S.C.

I /.

  • I I *1 "*1

'-=:.*===~==.-;;:-*=======P================-*i:=);i======!!======l'~=!=1=~'ij"'F'F==R==TTF1:!=r:===J""F===;t;t,=. =_ =.====.""',1======"=========

2-2-78 3-i-79

  • 04~10-78..

/

0*1-23-78 I \\t1 1 *

  • 1*

2-21-78 3"..i.10-78.

  • 04:-12-:-78..

. l 1ir-12*2"-rn.

I 3~ 10-7 s 1... 04-26-7 a...::i

'l1I I

.3~31.~78:'

  • 04~27-78.11'

.. I

--... 1 *..... * (*_**-. *.:::*.::.::-:*

  • ... *:_\\... *.; * *
  • ... _ j.. *.

'* fllJ I

'. 11*

I Pfll' i,'\\ ""1 '*'.'*,.. ',*.*I.... ;:*,.. : *": ' '*..

'.*... :._.:_... :>. i. _';-

I. :.

. *. */'" ;

i°t;

  • I I
'ii-sis*'.

. I "..

.. '* '..... 'I... ' '..'.

11. ' '.*, ". ' '

. u I*.

11.,,-

1:*: :*.i':: '.*:-*.,.),1*.. ",,'".'.,.:.

  • i,/ 1'.!:',:'."'".. *.'*;*,, 1/.:.,';*.*.,::..

II 11 II*. " :.: I"*,'".. ~ " ! :;\\h. : ' ~.

. *.*(*

(

c,, -' - _,, ;,

\\

-40,,..

"' - SENSITIVITY DATA

1.

Minimum Detectable Activity

a.
b.
c.
d.
e.
f.
g.

Gross Alpha; 5.27E-9

µCi/ml Tritium; 4.0E-6 µCi/ml Strontium-89; less than 3.0E+l pCi per total filter composite.

Strontium-90; less than 2.0E+o pCi per total filter composite.

- C02-14; less than 7.OE-10 µCi/ml.-

Strontium-89; less than 9.0E-9 µCi/ml.

Strontium-90; less than 8.0E-10 µCi/ml.

2.

Multichannel Analyzer - GeLi

a.
  • Liquid and/or Radiogases -

lOOcc --

Ba-La-140 I-131 Xe-133 Xe-135 Cs-137 Cs-134 Co-60 Co-58 Cr-51 Mn-54 Fe-59 Ar-41 I-134 I-132 Na-24 I-133 r-135" Kr-85 Kr-88 Kr-87 Kr-85rn

  • x~-138 Xe-135m Xe-133m Rb-88
b.

Radioiodines I-131 J:-133 I-132 1-134-1-135 2.0E-7 5.lE-8 5.4E 2.9E-8 9.2E-8 7.2E-8 l.5E-7 9.8E-8 3.8E-7

1. OE-7 2.4E-7
1. 6E-7 1.lE-7
1. OE-7
1. 7E-7
6. 9E-8

'4.'.5E'....T

. 1. 36E-5 5.5E-8 5.3E-8 2.3E-7

4. 7E-9_

5.8E-8

1. 7E-7 8.SE-7 2.3E-6 3.lE-6 4.7E-6 4.8E-6 2.0E-5 PROCED DEVIATIONS REVIEWED BY STATIO CLEAR SAFETY D OPERATING COMMITTEE AFTER TII LIMIT
  • SPECIFIED IN TECHNICAL SPECIFICATIONS APRIL, 1978 There were none during this reporting period.
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