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Informs of Status & Future Plans Addressing NRC Concerns Over Beta Radiation in Radioactive Liquid Effluents.All Releases to Be Performed in Batch Mode.Investigation Into Installing in-line beta-sensitive Monitors Continuing
	ML20128F810
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/17/1985
From:	Gahm J; PUBLIC SERVICE CO. OF COLORADO
To:	Johnson E; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
	P-85212, NUDOCS 8507080366
	Download: ML20128F810 (32)
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Company of Colorado 16805 WCR 19 1/2, Platteville, Colorado 80651 N

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June 17, 1985 Fort St. Vrain U*-

Unit No. 1 P 85212 Regional Administrator Attn: Mr. E. H. Johnson Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Docket No. 50-267

SUBJECT:

Beta Radiation in FSV Radioactive Effluents

REFERENCE:

1) G-84329, Johnson to Lee, Dated 09/04/84

2) P-84313, Gahm to Johnson, Dated 08/27/84

3) G-85096, Denise to Lee, Dated 03/11/85

Dear Mr. Johnson:

This letter is to inform you of our current status and future plans in regard to addressing the NRC concerns over beta radiation in Fort St. Vrain radioactive liquid effluents.

Concern over beta radiation, specifically in releases from the Reactor Building sump, first arose as a result of a release made on July 20, 1984 which exceeded the unknown radionuclide Maximum Permissible Concentration for beta radiation.

Subsequent analyses determined that the activity was due to sulfur 35, and that no Maximum Permissible Concentrations were exceeded.

This event was detailed in NRC Inspection Report 84-20 (Reference 1).

Public Service Company reported on this incident via Licensee Event jfj Report 84-009 (Reference 2).

Per this Licensee Event Report, the source of the radioactivity in the Reactor Building sump was J'

determined to be the drain line from a compressor in the helium U,

g purification system. The subject drain was plugged, and a survey of

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Q all drains in the Reactor Building was performed. A copy of the drain survey (T-252) is enclosed for your information.

The results of the survey indicate that all drains are correctly routed to either the Reactor Building sump or the liquid waste sump. We continue to believe that the July 20, 1984 event was an isolated case, and sample analysis results of the contents of the Reactor Building sump prior to and subsequent to the July 20, 1984 event confirm our belief.

These records are available for NRC review at Fort St. Vrain.

With respect to answering the NRC concerns as contained in Reference 3, the following actions have been or are being taken:

1)

Effective June 17 1985, all releases of liquid effluent from the Reactor Building sump will be performed in the batch mode in accordance with non-Technical Surveillance SR-0P-41-X,

" Volume (Batch)

Release from Reactor Building Sump".

A copy of this Surveillance is enclosed for your information. As you will note, prior to the release of any liquid radioactive effluents, the cortents of the sump will be sampled and analyzed for beta and gamma emitting radionuclides to ensure that 10CFR20 release limits are not exceeded. Subsequent samples will be taken every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months during each release.

2)

We are continuing our investigation into the feasibility of installing in-line beta-sensitive effluent monitors in the FSV Reactor Building Sump effluent discharge line. As discussed with Messrs. Phil Wagner and Blaine Murray of your staff, there currently do not exist commercially available on-line beta liquid effluent monitors. We have identified a beta liquid monitor being utilized in the biomedical industry, and we currently have this monitor on site for performance testing.

Although from a technical standpoint the monitoring system is workable, keep in mind that the transfer of technology from a laboratory environment to an operational facility is not always practical.

For example, the monitoring system requires very high purity water to function properly, and, as you know, the Reactor Building sump contents are less than pristine, to say the

least, vue to the multi-faceted nature of our investigation, we are not prepared to offer a target date for completion at this time. We will, of course, keep you fully informed of our progress and any developments.

Following the completion of our investigation, we would like to meet with you to discuss your concerns and our actions to address them.

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A We trust that the above actions will satisfy your concerns over beta radiation at Fort St. Vrain in the short term, and look forward to discussing our long term actions with you in the near future.

Please contact Mr. M. H. Holmes at (303) 571-8409 if you have any questions on this matter.

Sincerely,

/

J. W. Gahm Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station JWG:FJB/djc Enclosures

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- ' T. ; ' CO:nptny Cf (dGFSCfD 16805 WCR 19 1/2, Platteville, Colorado 80651 August 27, 1984 Fort St. Vrain Unit #1 P-84313 Mr. E. H. Johnson, Chief Reactor Project Branch 1 Region IV Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011

REFERENCE:

Facility Operating License No. DPR-34 Docket No. 50-267

Dear Mr. Johnson:

Enclosed please find a

copy of Licensee Event Report No. 50-267/84-009, Final, submitted per the requirements of 10 CFR 50.73(a)(2)(1) and 10 CFR 50.73(a)(2)(v).

Very truly yours,

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J. W. Gahm Manager, Nuclear Production JWG/djm Enclosure cc: Director, MIPC.

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.,,,,,,,n On July 20, 1984, initial analysis of the daily sample from the Reactor Building Sump indicated a higher level of tritium than the sample taken on the previous day.

The sample tritium activity was below maximum permissible concentration (MPC). However, releases from the Reactor Building Sump were terminated until the tritium levels were reduced.

The sample taken on July 21, 1984 indicated all radionuclides were below MPC, and releases resumed.

On July 26, 1984, a subsequent analyses performed on the July 20 Reactor Building Sump sample indicated concentration of unknown beta emitters was above MPC.

For a period of approximately 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months on July 19 and July 20, a release could have occurred that was in excess of MPC for unidentified beta emitters.

Releases from the Reactor Building Sump were terminated until the source of the high activity (unidentified beta emitters) was determined.

Maintenance activities concerning the helium purification system regeneration compressor were discovered to be the source of the unidentified beta emitters in the Reactor Building Sump.

The sump pumps were removed from service and plugs were installed in the ficer drains in the area of the compressor.

The floor drains will be routed to the Liquid Waste System rather than the Reactor Building Sump.

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On Thursday, July 19, 1984,at approximately 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months , with the reactor shutdown and depressurized for internal maintenance, the daily sample was taken from the Reactor Building Sump (T-7202) and analyzed, as usual, on the day shift. The analysis was normal with expected concentrations of radionuclides in the sump. On Friday, July 20, 1984, at 0244 hours0.00282 days 0.0678 hours 4.034392e-4 weeks 9.2842e-5 months , the daily sample was taken, and the day shift initial analysis indicated a higher level (but below MPC) of tritium.

The Radiochemistry Supervisor informed the Shift Supervisor that the releases from the Reactor Building Sump should be terminated until the tritium levels were reduced.

The Reactor Building Sump Pumps (P-7201 and P-72015) switches were placed in the

" pull to lock" position at 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months on July 20, 1984.

On Saturday, July 21, 1984, a direct Reactor Building Sump sample was taken at 0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months and analyses indicated that tritium, gamma, and gross beta activities were below MPC; the Shift Supervisor was i t. formed and the Reactor Building Sump pumps were placed back in service at 1055 hours0.0122 days 0.293 hours 0.00174 weeks 4.014275e-4 months .

On Thursday, July 26, 1984, the sample from July 20, 1984 was analyzed for gross beta activity and 35-Sulfur and it was determined that the concentration of beta emitters was 2.24 times the MPC (for unknown radionuclides) at the time the sample was taken on July 20, 1984,at 0244 hours0.00282 days 0.0678 hours 4.034392e-4 weeks 9.2842e-5 months .

It was concluded that sometime between approximately 0200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months on July 19, 1984,and 0244 hours0.00282 days 0.0678 hours 4.034392e-4 weeks 9.2842e-5 months of July 20, 1984, a liquid release into the Reactor Building Sump occurred from an unknown origin that increased the radionuc'lide concentration in the sump. The Reactor Building Sump Pumps were not placed in the " pull-to-lock" position until 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months on July 20, 1984.

For a period of approximately 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months , a release could have occurred that was in excess of the MPC for unidentified beta emitters. A decision was made that this occurrence constituted an Unusual Event, and State and Nuclear Regulatory Commission authorities were notified on July 26, 1984.

ANALYSIS OF EVENT:

Radiochemical analysis of the backup sample taken July 20 from the Reactor Building Sump indicated a beta concentration of 4.79E-05 pei/ml.

Based on the release rate of eight gallons per minute and the average cooling tower blowdown of 1632 gallons per minute, the calculated beta concentration released would be 6.72E-08 pci/ml. The MPC for unidentified beta is 3.0E-8 pei/ml, resulting in a concentration of unidentified beta 2.24 times MPC.

A sample of the July 20, 1984, sump sample was sent to an outside agency for a detailed analysis in order to determine the identity of the unidentified beta emitters. The results of the sample analyses have been received and have verified that no MPC values were exceeded during'this release.

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Other On July 19,

1984, at 1405 hours0.0163 days 0.39 hours 0.00232 weeks 5.346025e-4 months the helium purification system regeneration compressor was removed from service to repair a seal leak. Contaminated water was expected, when the compressor was disassembled. Any water released released, as goes into the floor drains of the regeneration pit, which was believed to drain to the Liquid Waste Sump (T-6201). During an investigation into the source of the unidentified beta emitters, dye was released into the drain and found in the Reactor Building Sump instead of the Liquid Waste Sump.

CORRECllVE ACTION:

On July 26, 1984, after it was determined a release could have occurred that was in excess of the MPC for unidentified beta emitters, the Reactor Building Sump Pump switches were placed in the " pull-to-lock" position while an investigation into the origin of the unidentified beta emitters took place.

After the source of the unidentified beta emitters was discovered to be the floor drains in the area of the regeneration compressor, the drains were plugged with inflatable plugs.

Public Service Company and the Nuclear Regulatory Commission conducted evaluations of continuous process beta monitors. Both Public Service Company and the Nuclear Regulatory Commission concluded that there were no instruments that would prevent a release of this type from happening again.

In an effort to inhibit a recurrencs of this event, the floor drains from the regeneration pit will be rerouted from the Reactor Building Sump to the Liquid Waste Sump.

No further corrective action is anticipated or required.

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INTER-DEPARTMENT MEMO - PUBLIC SERVICE COMPANY OF COLORADO h C-85-0 OATE:

February 13, 1985 T0:

Mr. Jerry McCauley, Results Engineering Supervisor, FSV FROM:

Jeffery Nadeau, Results Engineer, FSV ATTN:

SUBJ:

SUMMARY

OF DRAIN TEST-T-252 1

Oue to incidents in the past of unwarranted releases of radioactivity 4

into the Reactor Building sump via drainage lines, a test has been initiated in response to LER 84-009-00 which determines the destination of drain lines within the Reactor Building. As a result, there should no longer be any incident of accidental release of activity to the Reactor Building sump because someone uses the wrong drain to dispose of radioactive liquid waste.

The results of test T-252 are as follows:

Number of drains to Reactor Building sump 47 Number of drains to Liquid Waste sump 28 Number of drains that remain clogge,d/ untested 3

Total number of drains examined 78.

The drains that are clogged / untested can be reasonably assumed to drain to the Reactor Building sump.

If this is assumed, they will be labeled as such and no radioactive waste will be dumped into them and no accidental release will be made.

Also, these drains correlate very closely with the design that was intended (DWGs 8-148 through B-153).

The drains are listed under T-252 by description and location.

The method of testing these drains was either by visual inspection or by dye testing. A few drains had been previously verified. A letter 4

from the dye manufacturer is attached to verify its environmental safety.

Any questions should be directed to Results or to the conductor of this test.

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.Y~o PUBLIC SERVICE COMPANY CF COLORADD FORT ST. VRAIN NUCLEAR GENERATING STATION TEST REF. NO.

252 SYST. REF. NO. _ 62/72

,e REQUEST FOR TEST PAGE 1 OF 43 0L\\Lt %

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RECORD AND CONTROL OF ISSUE APPROVED AND ISSUED ISSUE PREPARE D BY PORC APPROVAL EFFECTIVE DATE OF N O.

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COMPLETED TEST R EVIEWED:

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FORM 372 22 3398

t PUBLIC SERVICE COMPANY OF COLORADO FORT SY. VRAIN NUCLEAR GENERATING STATION TEST REF. NO.

252 SYST. R E F. NO.

62/72 REQUEST FOR TEST g

PAGE 2 OF B 1 PURPOSE OF TEST To determine the flow path of equipment and floor drains in the Reactor Blda.

2 TEST OBJECTIVES Verify whether the eauipment and floor drains (reactor b1dg) drain into the Reactor Building sump or the liquid waste sump.

4 3 DESCRIPTION OF TEST (Use attached sheets if necessary) It is intended to trace out drains and their associated subheaders or headers in the Reactor Building.

First. the individual drains will be located as needed.

Then dye will be poured and flushed down the drain thus allowina the tester to trace the drain to one of the sumn pits. All drains tested will be documented on the following data sheets.

4 DATA REQUIRED (include applicable data sheets and integrate with procedure if possible) include room for "Remarki Equipment description / floor drain Location Drain (Reactor Bldg. or liquid waste sump)

F ORM 372 22 3399

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.e PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION TEST REF. NO. 252 SYST.REF.NO.TT72 REQUEST FOR TEST PAGE 3 OF 13 5 ANTICIPATED RESULTS:

All significant equipment and floor drains will be traceble to either the Reactor Buildina sump (T-7202) or the liquid 3aste_ sump (T-6201).

6 ACCEPTANCE CRITERIA: None.

i NOTE: UPON COMPLETION OF THE TEST, DATA SHALL BE APPROPRIATELY AN ALYZED AND TEST RESULTS AND RECG'./E T ; J-TlON AND/OR EVALU ATION SH ALL BE SUMYARIZED AND PRESENTE D TO THE SUPEHINTENCENT OF OLER ATIC,r.! 5 24 SIN AL APFROVAL AND FURTHER REVIEW BY PO4C AND THE NFSC AND/OR FURTHE R REFORT AND OGCUME'.T A's;.

R E QUIR E M E N TS.

l F OR" 3 72 22 3400

PUBLIC SERVICE COMPANY GF CELCRADO FORT ST. VR AIN NUCLEAR GENER ATING STATION TEST REF. NO.

252 REQUEST FOR TEST PAGE 4 OF 13 7 PRECAUTIONS, LIMITATIONS, AND SPECIAL ASSISTANCE (INCLUDE PROVISIONS TO VERIFY THAT LIMTA-TlONS ARE NOT EXCEEDEDh Follow S0P 62 and S0P 72.

Particular drains may require the attention of Health Physics and/or Radiochemistry. Also, consult Operations, Radiochemistry and Health Physics about draining the sump pits so the testing can continue.

Suggestion: Use two people, one at the drain and one on level 1 for each drain trace test.

Beware of testing too many drains and increasino the concentration of dye in the sump pits beyond the point where additional dve tests become undetectable.

Use different colored dyes, usino the the lightest color first.

Special Assistance: Ooerations. Health Physics and Radiochemistry.

8 STANDARD OPERATING PROCEDURES S0P 62 and 72.

9 SAFETY EVALUATION See attached.

[0RM 372 22 3401

PUBLIC SERT ICE COMPANY OF C'dLCRADD FORT ST. VRAIN NUCLEAR GENERATING STATION TEST REF. NO. 252 SYST. REF. NO. 62/72

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REQUEST FOR TEST PAGE 5 OF 13 10 TEST EQUIPMENT (IF REQUIRED)

NAME IDENTIFICATION NUMBER LAST CAllBRATION C A E Test dve N/A N/A 11 TEST CONDUCTOR (INCLUDE ALL ASSISTANTS)

PERMISSION TO INITI ATE TEST N [.

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POmu 372 22 3402

T-252 Page 6 of 13 7'.

Public FORT ST. VRAIN NUCLEAR GENERATING STATION (WSerVlCe Pusuc SERVICE COMPANY OF COLORADO f~

12.0 Procedure NOTE: There is no particular sequence in which the drains that are listed on the data sheets should be traced.

Please reference section 7 of this test.

12.1 Reference the following data sheets and locate the piece of equipment or floor drain.

12.2 Pour dye into the drain and flush the solution down with water.

12.3 Visually verify whether the dye drains into the Reactor Building sump or the liquid waste sump.

12.4 Record which sump pit the dye drained into on the data sheet.

12.5 Repeat steps 12.1 through 12.4 until all drains have been traced.

FORMIB)372 22 3643

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l l Sample Line l

l l

l l(V-6226) Floor l Wall No. 39,and No. 40 l

l l

l rr.,w...w l

2 l

l l

l c,-

l l

l 4

l l Floor.

l Wall No. 36' and No. 37 l

l l

I l

l l

l lP-6202/6202S Liquid Waste l

J l

l l Floor (2) l Transfer l

l l-

-l l

l l

l 4791' l

cc.wpuc lN. Wall, Emergency Eye-Wash l l

l Lvl 5 l Floor a$

l Station.

l l

l l0ne Floor Access Plate l

l l

l Pit (Floor) lbetween the following:

l l

lAbove F-6201/6201S, F-6101,l l

l

{

lA-6201/62015, F-6301/63015,l l

lF-6302/6302S and i:-6304.

l l

' ll l

lAll of the pit drains drain l l

l linto the same header.

l l

^9 l

l l

c'l 1,1

-- e, & (

l

{

l l _.

il

,l l-4829' l

~

l Q, l b l

l l

.I Lvl 7 Floor Health Physics Shower l 4839' l

lP-4601/4601S Cooling Water l l

l Lv17h l Floor l Wall No. 85 l

l V.

l l

/

~1 l_

l _

'p

/

l l

lP-4602/4602S Cooling Water l l

1,/,,

l l Floor l Wall No. 87 gc l

l l

e k

F08tM18)372 22 3643

/.

1I

E T-252

{

Page 10 cf 11

'(C/S Pubila FORT ST. VRAIN NUCLEAR CENERATING STATION ervice rusuC SERVICE COMPANY OF COLORADO l ELEV.

l EQUIPMENT /0 RAIN l LOCATION l

DRAIN l

l(FLOOR)l DESCRIPTION l l (RX BLDG SUMP)/

l l

l LIQ WASTE SUMP) l l

l l

l 4839' l

lN. of C-2301S l

l l Lvl 7h l Floor l Note: This drain is one of l l

l l

lfive drains that drain intol l

l l

la common header visible l

l l

l lbelow the platform.

Other l l

l l

s,f l equipment in F-2301, F-2302l l

l l

r' lA-2309/23095, F-2304, l

l l

l lC-2301, and E-2307.

l l

l 4849' l

lA-4601/F-4601 l

ffy81 l Lvl 9 l Floor gf lDemineralizer/ Filter l

l l

1 l

Sl 1 $

lA-4602/F-4602 l

l Demineralizer/ Filter l

g l

Floor l

l l

l l Floor j

l Hot Service Facility l

l l

l 4864' l

lC-1301/1302, Fuel Handling l l

l Lvl 10 l Floor f. $

l Purge Vacuum Pumps.

l l

l l 4881' l

l l

l l Refuel-l Floor l

l Regeneration Pit l

l ling l

l l

l l Floor l Bed Drains lP-4605/4605S Glycol Water l l

l l(Funnel) l Pumps l

l s

l l

4i l l

l l

l Sample Line - / lS-4602 Nitrogen Recondenserl l

l l(V-4614-85) ~ l Chiller NW Corner l

l l

l Floor lE. Wall Betweem 7L and 7K l l

l l

l l Center of Refueling Floor l

l l

l Floor lBetween 4 and 4A, approx.

l l

l40 ft from J Wall l

1 l

l l

Y l

l

\\

l l

FOW:Bt372 22 3643

Oe f

'9*

PUBLIC SERVICE COMPANY OF COLORAD@

~

FORT ST. VRAIN NUCLEAR GENERATING STATION TEST REF. NO. 252

"U' REQUEST FOR TEST t

PAGE llOF t$

13 VERIFY THAT THE SYSTEM HAS BEEN RETURNED TO NORMAL:

O

$Y i....,..............i

/

/....

14 TECHNICAL SERVICES ACTION:

10 CFR 50.59 REPORT REQUIRED YES O NO TECH SPEC REPORT REQUIRED O YES NO REVIEWED BY (E

I a.....

l l

I FORM 372 22 3403

)

t FORT ST. VRAIN NUCLEAR GENERATING STATION J

Public CN/TCR/SCR/PCh

) SerVICO" PUBLIC SERVICE COMPANY OF COLORADO NO.

2 53 SAFETY EVAL.UATION PAGE J'kW 6 i

CATEGORY TYPE:

U CN OVERALL U CN SUBM:TTAL U SETPOINT CHANGE REPORT N TEST REQUEST U TEMPOR ARY CONFIGURATION REPORT U PROCEDURE CHANGE IFSAR)

U OTHER CLASSIFICATION: ARE THE SYSTEM (S) EQUIPMENT OR STRUCTURES INVOLVED, OR DOES THE ACTIVITY AFFECT:

CLASSI

[ YES N NO ENGINEE RED SAFEGUARD U YES S NO SAFE SHUTDOWN U YES N NO PLANT PROTECTIVE SYSTEM C YES E NO SAF ETY RELATED U YES E NO SECURITY SYSTEM U YES X NO REMARKS _RG4c-TW2._ SCI-P/NI 0M M ELow PA ITN f 781 C_

l t

5 ff.15. lf.) g [eN IN R.fi'lE RW'. nim N C 1.

DOES THIS ACTIVITY AFFECT STRUCTURES. SYSTEMS COMPONENTS. EQUIPMENT. TESTS. EXPERIMENTS OR PROCEDURES t

DESCRIBEDIN THE FS AR OR TECH SPECS)

U YES N NO I

LIST THE APPLICABLE SECTIONS REVIEWED _TN/L_{Q ort ___f44fus_ gyp _Aow % g g _pg4,wf_ 6..

/WIo+s_ tra g _ & a r.__to an cge g n jw_ ti m _ E,rn y on tea.u_cfarc s.

t

'i 2.

DOES THE ACTIVITY REQUIRE THAT CHANGEIS' BE MADE TO THE FSAR OR TECH SPEC)

U YES h NO I

LIST SECTIONS TO BE CHANGED AND THE CHANGES TO BE MADE- _____

r 3 DETERM!NE WHETHER OR NOT THE ACTIVITY INVOLVED IS AN UNREVIEWED SAFETY OUESTION UTILIZING THE FOLLOWING GUIDELINES-f tat HAS THE PROB ABILITY OF OCCURRENCE OR THE CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUIPMENT IMPORTANT TO SAFETY PREVIOUSLY EVALUATEDIN THE FSAR BEEN INCREASED)

}

U YES b No STATE B ASIS - Tt'ds6 DM imL art al?-.N O T__ E G B k k-_/ N 7'o.

ne war _uv _n ay_n c cicuran rms__r=n a.

I i

F

'B) HAS THE POSSIBILITY OF AN ACCIDENT OR MALFUNCTION OF A DIFFERENT TYPE THAN ANY EVALUATED PREVIOUSLY

' YES X NO STATE B ASIS.. THI3 _ Aow. @ W._ J/TS7 _ __ _

IN THE FSAR BEEN CRE ATED' W LL tv 0T JH.rttr - T++e_ Newt __ofWrro n ck__rws.rac_Cn4nvt

'Cl H AS THE MARGIN OF SAFETY, AS DEFINEDIN THE BASIS FOR ANY TECHNICAL SPECIFICATION OR IN THE FSAR BEEN REDUCED' U \\ES Y NO STATE P ASIS TU646 IS

/V o __ M nd G iov _ o F_ _ SM67y__._

.NSociserap-_ wirn__tssne xmin n_nmas_w enrc n ms_tH saEu --

fare r. ___

DOES THE ACTIVITY APPE AR TO INVOLVE AN US.REV:EWED S AFET) QUESTION YES N NO BE S AF ET v SiGNihC ANT

$ YES N NO

__ _/ t hlo

.Y__

B)

CsuY M

/ /[ s 8f __ _

APPROVED _

L_

n.M

%v %

et s use o

~

PUBLIC SERVICE COMPANY OF COLORADO FORY ST. VRAIN NUCLEAR GENERATING STATION CN

r

__d_

'h ENVIRONMENTAL EVALUATION No.._ _ 2 12 PAGE _($ Wi$

f

. corn m m un

-~

E431@IC; W r-

-!FR260M@M F54-E _- T 3aa,MS3kh-TYPE:

T CN Overa!!

CN Submittal Other____ 1 4 Are ali measurable nonradiologica! (ffects of the activity confined to the o -site areas previously disturbed during sle p'eparation, plant construction or prevous r/:.nt c;wstior?

>< Yes Na State basis A_f._L_Ac_to y gx; gg s ___ p q c n., rw____ __m__3f+;g _ __ _7 n.rf jytut

.JK@GMs

-rv__- THs rieAr ro n-_ _. 6 a tJ-cins _j._ _

Is the activity required to achiese comptance, tt Ftdera!, State or local envirc enta! regulations?

~ Yes k.o t;on 11c,rne ans.w as s es the a r wr, a:es o v.r e umen.wn en.acnmenu c non Sgn ans are r^e 1 m I'trorn rcws ai '

the atr vro h.<s tnc poh n 0 *o ve." ~p s.

-n

.wic wuwou'auestwn C: n < re :% rems u c't u es a%3rcn t:'m E W/d Uld 1 (d M UMY. t G W WM IlWW MI*E:'G'W ^mf%2F2 umM-

=

mtm.em 'IE$1 Nc 1

is the activity identif red in the f.n :er n v

-+

Or Supplementary Enwronmems Dnunu e iSr 0-3 ?

Identdy documc.ts and docuwnt st

t. *re.

c. e e

m.--

.-.--.a

-.*---s-

~

., - - - + -. =

m---.-...--.-ew 2.

Duenne v.1 t'rer c r,o: the ce: c' r.,

o, ; et me.ed e nvor - td quest or os ng the foPowi,g gdde m (if the anse,er to any of the t0!.a/.ng cuesncns is Yes then this ac.:.tv invo!,es an unreviewed environme t3:

question.)

(A) Wdi this activity result in a sgn:fcant invease in any adverse cmi :nmenta! impact previous!y evaluated ir ve FES?

Yes te State basis: _. _..

(

(B) Wdl this actinty result in e gn:' a t c Vc

.n the t, pes, or a signb. Ent increase in the amounts of effiuents ; a significant increase in the autha ver: c _ u ie,P Yes No State bac e LC.

Das t% act nas-c.

..nda;

. r FES

'r u te 5

_ ____-.._ _-. _. _ _ _ _. _.. _... _ _ _. _. _ _.. _.. - _ _ - _. ~ -.. _.

e,

.-.,o,,ts-'

w x Ne DCe5 the acti,its,nve ve a um I

C Bv.

_ _.. 1 Il 2/ 84

.;rea.'ed-d [.4st W[ 4.4$tfl

.// d6 /[

t

! ~_

T i'.

s *

' s!

s l

l l

l

T-252 Page 12 of 13

. '/

N Pub.Ila FORT ST. VRAIN NUCLEAR GENERATING STATION 3

( y Sorvic ^J" rusuc ser.vice comeAmy or cot nano

(-

l ELEV. l EQUIPMENT / l LOCATION l RX BLDG l

METHOD l l(FLOOR)l DRAIN l

l SUMP /

l l

l l DESCRIPTION l l LIQ WASTE l l

l l

lTurbinel,,

l l

l y,%.

l l Side I

rnus I w b we, unu_

l u* -

l ri t.s..no l

l

1. I rh 4 E 46 ' - l C-l asr Ivy,,P i l

l l

l l[2{M$ s4 l

l l

l

2. l Filter drain lF-7304 l

TA l

l l

4864' l l

l str.

I 't ai 8 l((['do l

l l

l

3. l Filter drain lS-7301 Rx Bldg vent air l TN l

l l __

l 4885' l l

lr6 l

l lD l Tech l cec hood l

l lServicel7/[*d*#

l l u o.

l l

l Bldg l Sink (

l Chemical Labs l w #.

l 3-I4' '

l l

l 1

l

~

Test Conductor Signature Date r

/

FORV(C)372 22 3643

[

INTER-DEPARTMENT MEMO - PUBLIC SERVICE COMPANY OF COLORADO PPC-85-0634 DATE:

February 13, 1985 b

T0:

Mr. Jerry McCauley, Results Engineering Supervisor, FSV FROM:

Jeffery Nadeau, Results Engineer, FSV ATTN:

SUBJ:

SUMMARY

OF DRAIN TEST T-252 Due to incidents in the past of unwarranted releases of radioactivity into the Reactor Building sump via drainage lines, a test has been initiated in response to LER 84-009-00 which determines the destination of drain lines within the Reactor Building. As a result, there should no longer be any incident of accidental release of activity to the Reactor Building sump because someone uses the wrong drain to dispose of radioactive liquid waste.

The results of test T-252 are as follows:

Number of drains to Reactor Building sump 47 Number of drains to Liquid Waste sump 28 Number of drains that remain clogged / untested 3

Total number of drains examined 78 The drains that are clogged / untested can be reasonably assumed to drain to the Reactor Building sump.

If this is assumed, they will be labeled as such and no radioactive waste will be dumped into them and no accidental release will be made.

Also, these drains correlate very closely with the design that was intended (DWGs B-148 through B-153).

The drains are listed under T-252 by description and location.

The method of testing these drains was either by visual inspection or by dye testing. A few drains had been previously verified. A letter from the dye manufacturer is attached to verify its environmental safety.

Any questions should be directed to Results or to the conductor of this test.

.G/m h/Is-

~7 fe W Nafieau JF/dal Attachments (2)

]t]/ SeTVICO PilBtIC SFRVICE COMP ANY OF cot OR ADO

/

l WNC N

'1 l

Fapt

/

cf

,/

PROCEDURE DEVI ATIOt.! REPORT

m.,:... g 0..

p.... n.,..:

s.

...ar.

y

'T~ "'.5~2.

l1 3 F3T' FIV E.* F.EC'Ji?.E:

I YE3

'M:

L n PDF.C FIVIEU 25 FIOUiFIC., THE IliiTI ATOE IS FISP0fiSIELE TO Eli3U?I TH~T THE PDT. II 1

SU3F.:TTED FOR PORC FIVIEW lid LATER THAfi 14 DAYS FRD.V. THE PDR IM?LEMEliTA m :. :

CHAfiEED FRO.:

l CHAfiGED TO REA50!i FOR CHAfi3E N55 ",k!'. !

F......

i I

^'"

'b f c.c5 Tiny trsT m g or

! ggyj i ts-T'

-re i9u.ubt LIST e4 A v8*.

D E f. *J N f5% E b

% L%

9.g bh6 AbD76DNAL Wb'b hY Ta t, o su(=s u A L, 657*

g A* REvis En Lotmd s5

%lzLFotL, Tr4 L HE W s.*s ~~

'k brse,.n s P Ta p a (TX%C%

1-'O vVss L IssLLLJ DC MCCC pge n us TH e4 N T"r'i C O Cs68^/ E (pngs y - s t

F TH L 11'.

LDLA Te D^l o

y r4y bESLCeP T* D As % W e a.,L.

B E.,

KitVit 6D "t O ALA.t' d fCR

~

'DE Soca,Aln Torna M cC E.

Ma s'ATL v E A Ls4 bt4:AJ,

l ItilTIATOR:

d[rer Mb

'2.Z3-W V 'l61f/LAI URt. )

( U Al t. )

DEVIAT10?1 CA. ORY:

,Tff',PA Y

PEPNJiEtiT - DCCF ATTACHED

.~/7/ G g-/f-fly SUPERVISOR:

)

/

6 6f.Alukt) ~

tuAlt)

- I A /)

//

APPROVALS F

W BY: h f!} & 2 BY: )fh p, f GFLA hiiASEiElii Si. Fl DATE (P il FJJiAGEMEtiT STAFF - SRO) l BY: BY: (PT6CEDURE AUTHORilER) (DATE) (PROCEDURE AUTHORIZER) (DATEJ BY: BY: TD.OCEDURE AUTH3RIZERl TEWTET TPROCEBUREAUTHORIZER) (DATE) ~ PORC: ~~~ ~(BATET (ME E iIt.'G i;.'.".iER) 3111AiCR: FOR',;*.RD OR15:'; AL T3 F0fC r. E:y,, A77:CH CG?Y TO TP.0:E;'JRE Belt;G DEVI ATED.

T-252 Page 7 of 13

/D Public FORT ST. VRAIN NUCLEAR GENERATING STATION O/ SCIVl' C/"

PU!UC SERVICE COMPANY OF COLCRADO J ( l ELEV. l EQU1PMENT/ l LOCATION l RX BLOG l METHOD l l(FLOOR)l DRAIN l l SUMP / l l l l DESCRIPTION l l LIQ WASTE l l l l l 1 I I l 4740' l l l lg l l Lvl 1 l lC-2401 He Transfer Comp / l gj l l l

1. l Floor (2) lSE Corner l

l l l l l l 1 I l l l l l l l 2. Floor (2) East Center Room n l l lC-6301/C-63015 gas waste l l gl l

3. l Floor (2) l comp West of each tank l

g l l l l l l 1 l l l lC-6301/C-6301S East of l lg l l

4. l Floor (2) leach tank l K )(

l l l l l l l g.;- l l l lC-6301S behind tank in l lg l O 5. Floor Iback l g l gy-l lAlong wall South of liquid l [ l hh l l l waste sump l l l 6. Funnel l I I lua. I I l

7. l Floor lP-6101 Chem supply room l gg, lbw q

l l l l l l l l 8. Funnel lSE wall by elevator l M l l Eg l l l l l l 9. Floor NE of keyway near T-2112 RK l l l North keyway near l Ihw l l

10. l Floor lC-2107/2107S l %X lg7 l

l l l I l l 11. Floor NW of keyway lM I I I I IT"" l l l lT-2112 gas pressurizer lD l l l

12. l Funnel lnear #9 l

l l g l l l 1 1 I l l lT-2113 gas pressurizer l l l$ g 13. Funnel near #9 l l l lAgainst wall north of l%% l l l

14. l Funnel lC-2107/2107S l

l l l l I I I"# I 15. Funnel Near P-2103 North keyway lM y i I I I I I FORViC1372 22 3643

T-252 Page 8 of 13 7 1Public FORT ST. VRAIN NUCLEAR GENERATING STATION DServlC9" PUBUC SERVICE COMPANY OF COL'IRADO i l ELEV. I EQUIPMENT / l LOCATION I RX BLOG l METHOD I l(FLOOR)I DRAIN l l SUMP / l l l l DESCRIPTION l l LIQ WASTE l l l l l l l l 16. Funnel INear P-2103S North keyway KX lh[g I I I I I I 17. Funnel Next to 15 ff. I c_(, l l l l l 1 I I I I I I I I

18. l Funnel l North side E-2101/E-2106 l 'R.X l DTE l

l l l l 17" l l l l South of 10 North keyway l Qu l do 10 l l

19. l Funnel lagainst wall lM l *iwhol-l l

1 l I 20. Funnel South side E-2101/E-2106 D \\ 21. Funnel Near P-7202 North keyway y i I I I I w. l l

22. IFunnel l East of 20 West of keyway IV l gr i

i I i i l l l 23. Funnel lF-2103/2103S I4 hfsr I I I I I I l l l South of 23 along wall l lm I l

24. l Funnel lS-2103 I ~R_%

l i g I I I I I I l l l l lE2104/21045 North S/24 l4 I 1 l l

25. l Funnel lalong wall 7

l l l l l 1 I I l West of keyway center of I l bW l l

26. l Floor lwalkway near 23, 24, 25 I RX l rt.W l

i I I I I I 27. Funnel E-2104/2104S South D l 7 l l l l l l l l Iloop 1 System 91 SW of l9 Im l l

28. IFloor l keyway l

l I I I I I i l l l l Loop II System 91 East of I Iw l I

29. l Floor l28 l E%

l Ttsr I I I I I I I I I I lBehind Loop I by south wall l (.+c9g o l I I l l l

30. l Funnel 1

I I I I I I l l I Iww I I

31. l Funnel lF-2101/2101S I

E% i "','g i i i I i I . m o n. - 1 FORM (Cl372 22 3643 J

T-252 Pag? 9 of 13 '/ D PubllC FORT ST. VRAIN NUCLEAR GENERATING STATION h/ SCIVlCO* PUZLIC CE'JNICE COMPANY OF COLCRADO i l ELEV. l EQUIPMENT / l LOCATION l RX BLDG l METHOD l l(FLOOR)l DRAIN l l SUMP / l l l l DESCRIPTION l l LIQ WASTE l l l l l l l l l l l North of Loop II by South l lQ l% l

32. l Funnel l wall l

l l l l l l 1 " l I I l l l l l

33. l Floor l Steam / Water dump tank l g l

[ l l l l l l l l l lNear P-2101S BW pump 10 l l* l l

34. l Floor lSE of keyway l

R% l l l l l l l W I l l Clean-out lDirectly West of 34 near lD lb%, l l

35. l Opening l wall l

l l l l l l l S' l l l l South of 34, 35,4 lines l l l l

36. l Funnel l drain l

RX l l l l l l l l 37. Funnel E-2105/21055 l O' l g l l l l l l l l l l 1 1 I l

38. l Funnel l West of 37 in same room l @

l Ng l l l l l l l l NOTE: Upstream line comes off of main header to keyway and spills l l into elevator shaft in case of downstream clog. l l l l 4756' l l l l visat "*l lIW5Pf2 l Lvl 2 l l lLW-l['f,$ dig l l

1. l Floor lNE corner wall #33 l WE l

l l l l Im da' l l l North wall #29 beneath l l l {^ l

2. l Floor lHV-2133-2 l

dr. I l I _I I I I l l 4771' l l l l l l Lvl 3 ISample line lT-6101 level indicator I a.ocAc6 l l l

1. lV-6156, Funnel l drain l

l l 1 1 I I I I l l l l l visa a'7 l l

2. l Floor (2) lT-6101 through crawlspace l $h QT$

] I I I I l as l l l l East of T-610 chentcar l" 6 l l l

3. l Floor (2) lsto om REs "

l l l I l l ce'"6e ""7 l l l l l l luc l

4. l Floor lHP laundry lwC l 2"a #

l l l l l l l l l l sesa: l l l l h l"f"7,,7;tl l

5. l Sample bin lNear 46 system coolers l

l l l l l l c.o-ast.i FORM tC)372 22 3643

T-252 Page 10 of 13

Im, 's Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION b SCIVlCG*

PUILIC SERVICE COMPANY OF COLORADO I l ELEV. l EQUIPMENT / l LOCATION l RX BLDG l METHOD l l(FLOOR)l DRAIN l l SUMP / l l l l DESCRIPTION l l LIQ WASTE l l l l l l l l l l l l v a.. lv eduai. l l Q. a%R l l

6. l Funnel (2) lNext to S-7320 HVAC l

psy, l

- w t.l l l l l l l l'C' Circulator accum drains l C L lv u.c - l l cons T* l

7. l Funnel lthrough fire door l

/ l 3" "t ll l l l l 8. Funnel 'D' Circulator accum drains Ef l Sfs"k l l l l l l l l l l l l 9st l l

9. l Funnel l'B' Circulator accum drains l E%

l As 7 l l l l l l l l l l l lbs wsf I l

10. l Funnel j'A' Circulator accum drains l 4%

Fr,s.ao l l_ l l l ld """'I l 4781' l l l l #'IsN'r$ l l Lvl 4 l l l"# h, l l "*5 l

1. [ Floor l Wall 41 l

l

LD. ll l

l l l l l 1 l l l l

2. l Floor lC-6302/6302S Nitrogen Comp l dr l SQ l l

l l l l l l l l lua I sw I l

3. l Floor l Wall 39/40 l

l

s t l g

l l l l l l l l l l l saut l l

4. l Floor l Wall 36/37 l (Q l

r g l g l l l l l l l l lP-6202/6202S liquid waste l l g wt_ l l

5. l Floor (2) l transfer l

l As l l l l l c,o I sast l l

6. l Sample l West / Fuel well wall

! gr I as g l l l l -(v - u M l l l l 4791' l l l l q,wau - l l Lvl 5 l l l 'Q l r,cs zeo l l

1. lFunnal (2) l0n stairwell either side l

lsi " " * -l l l l l l 5es

1 "d l l

l l lu a. I b vr 7e.srl l

2. l Floor lN. Wall eyewash station l

wW l.r.ss no l l l l l l"6 "" 9 l l lOne floor access plate to l v a. l w g1.,, l l

3. l Pit

[the following: N #'/6

5 l W si' l M' -

l l l l A bM'/aois, F -W8/Oc6 U#' hs l "YWM[ l l l luw l 9,wu l l

4. l Floor l Truck Bay l u %-r-lqAs,gm l l

l l l l l FORM IC) 372.%. 3f43

T-252 Page 11 of 13 Publia FORT ST. VRAIN NUCLEAR GENERATING STATION 7,4 )SCIVlCD* C/ PUZLIC CERVICE COMPANY OF COLSRADO l ELEV. l EQUIPMENT / I LOCATION l RX BLDG l METHOD l l(FLOOR)l DRAIN I l SUMP / l l l l DESCRIPTION I l LIQ WASTE I l l l l l l l l 4829' I I l l l l Lyl 7 I I I ua. l *.d I I

1. IFloor (2) lHP shower (Turbine side)

I wsr I l l l l l l l l l l l lM I l

2. l Sample l North wall luo I r.cs * **

l l "f. NuiF

*T l

l l l lf*nl l lu lW l

1. IFloor IP-4601/4601S wall 85 l

l m th '# Q l l I l l W "9 ' I I I I l v.swau l l

2. IFloor lP-4602/4602S wall 87 l K )4 lms. ro l l

l l l ITT l au-1 l 1 I I lan I

3. ISample line IN. wall fire water station I vg I

egg,l l I l l meK l 4849'_I l l l l l lD

l l Lvl 9 l lA-4601/F-4601 lN l * %r l l

1. l Floor ldemineralizer/ filter l

Ims '" l l l l l l l lA-4602/F-4602 I Iw I l

2. IFloor ldemineralizer/ filter IRK I sage.

l l l l l l l d" l l l l l 2..M l l

3. l Floor lHSF l u g, l

l l l I 1**' I Ci 1 4864' I I luo. l 9 iw'( - l l Lvl 101 IC-1301/1302 fuel handling l * #- lms,co l l

1. l Floor l purge vacuum pumps l

lM5 l l 1 I I l '" " 'E I I 4881' l l l l l l Lvl 11l l lcso. g q,g I

1. l Floor l Regeneration Pit I

l l l l 1 l l , c.s. I I 1 IP-4605/4605S glycol water l ly, # a,6 "P. 1

2. l Funnel l pumps lQ lia'a

5 I

I I l l

Mis I l

l 15-4602 nitrogen recondenserl l l l

3. l Funnel Ichiller l Ri l94 l

1 I I I I Z l I I l 1.p*~ ' ri o ' "' " l l e,sA - l l

4. IFloor IE. wall between 7L & 7K iluo d l4 l

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5. IFloor l Center of refueling floor I fC%

l}'$ '[ Ml l I I l l a m a. I FORM IC) 372 - 22 3M3

T-252.Jh INTER-DEPARTMENT MEMO - PUBLIC SERVICE COMPANY OF COLORADO U PPC-85-1166 DATE: March 21, 1985 T0: Mr. Jerry McCauley, Results Engineering Supervisor, FSV FROM: Jeffrey Nadeau, Contract Results Engineer, FSV ATTN: SUBJ: SUPPLEMENT TO MEMO PPC-85-0634 IN RESPONSE TO MEM0 PPC-85-1089 In memo PPC-85-1089, Item 4, it was noted that the floor drain for the System 47 heat exchangers (E-4701 and E-4702) on Elevation 4756 do not appear on the drain list in T-252. This is correct. However, this drain had not been overlooked during the carry-out of the test. At one point, a dye test was being performed on the clogged Level 3 floor drain. A downstream clog forced the flow up and out through the unlisted drain and Health Physics performed a survey of the spill. This verifies the connection between this drain and the one clogged en Level 3. The drain in question was inadvertently left off the list. Results intends to have the clogs cleared by contractors as soon as possible. This will clear the drains listed as " clogged" in T-252 as well as the unlisted drain mentioned above. Y W feffrefhaceau JN/skd cc: PPC File u

s INTER-DEPARTMENT MEMO - PUBLIC SERVICE COMPANY OF COLORADO PPC-84-3562 DATE: December 4, 1984 r T0: Manager, Nuclear Production FROM: Peggy Collins, PORC Clerk ATTN: SUBJ: PROPOSED SPECIAL TEST T-252 In PORC meeting #598 on 12/3/84, the Committee reviewed Proposed Special Test T-252. The following is an excerpt from that meeting: "The Committee reviewed Proposed Special Test T-252. The purpose of this test is to determine the flow path of equipment and floor drains in the Reactor Building. This test will verify whether the equipment and reactor building floor drains drain into the Reactor Building sump or the liquid waste sump. Special assistance will be required by Operations, Radiochemistry and Health Physics. The Committee found this not safety significant because the test does not increase the probability of an accident and no new accident modes are generated. This is not an unreviewed safety question." Please review this test with regard to Technical Specification AC 7.1.3.7, and advise if you would like me to forward to the NFSC for their review. .R.QQte Ntgy' Colli ns /pc Attachment Please forward only this memo to the NFSC date v Please forward this memo and attachments to the NFSC date /f/ /hf e /,/ax, ~Xp(IN~~ f,n:cx x 4 san,w s,

PUBLIC SERVICE COMPANY OF COLORADO SR-0P-41-X Issue 1 , 't FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 6 8 TITLE: VOLUME (BATCH) RELEASE FROM REACTOR BUILDING SUMP DEPARTMENT: OPERATIONS ISSUANCE AUTHORIZED PORC EFFECTIVE REVIEW PORC S 0 0 DEC 211984 DATE l2,-2 l-S 9 Do not start test before Week # and must be completed by Sch. Clerk This procedure cannot be run in its entirety for the following reasons: 1. This system is not operating. 2. This system is not required to be operating and has a frequency of one month or less (reference Technical Specification, paragraph 2.18). 3. Reactor is in " scrammed" condition. 4. Loop I is in " Loop Shutdown" condition. 5. Loop II is in " Loop Shutdown" condition. 6. 1A Helium circulator is in " tripped condition". 7. IB Helium circulator is in " tripped condition". 8. 1C Helium circulator is in " tripped condition". 9. 10 Helium circulator is in " tripped condition". 10. Other 11. Reschedule test for Department Supervisor FORM 372 - 22 3f 42

SR-0P-41-X Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 6 SerVICO PUBLIC SERVICE COMPANY OF COLORADO 1.0 PURPOSE To ensure proper equipment in service prior to starting volume (batch) release from reactor building sump. 2.0- PRECAUTIONS, LIMITATIONS, AND SPECIAL ASSISTANCE Health Physics 3.0 PREREQUISITES 3.1 Test Equipment Last Calibration Name Identification No. Date None i 3.2 References 4.0 AUTHORIZATIONS 4.1 Departmental Approval Dept. Supervisor Date 4.2 Mech /Elec Clearance Issued, if required: Number N/A 4.3 Radiation Work Permit Issued, if required: Number N/A 4.4 Permission to initiate test Shift Supervisor Date tonvreim n m

SR-0P-41-X Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 6 SerVICO PUBLIC SERVICE COMPANY OF COLORADO 5.0 PROCEDURE 5.1 PRELIMINARY CHECKS 5.1.1 None 5.2 TEST PROCEDURE 5.2.1 Notify Health Physics that a volume (batch) release is needed. 5.2.2 Obtain completed lab analysis for a volume (batch) release from Health Physics. 5.2.3 Notify Health Physics that you are going to start a volume (batch) release from reactor building sump. 5.2.4 Ensure continuous sampler is in service prior to starting release. Health Physics Signature 5.2.5 Perform valve lineup per S0P 62 for a volume (batch) release. l l Test Conductor Signature Date FOWiP!372 22 3643 I

SR-OP-41-X Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 6 SerVICO PUBLIC SERVICE COMPANY OF COLORADO 5.2.6 Notify Shift Supervisor that volume (batch) release has been started. 5.2.7 Notify Health Physics volume (batch) release is completed. 5.2.8 Ensure that a sample is collected from the continuous sampler at the completion of the release. Health Physics Signature 5.2.9 Notify Shift Supervisor volume (batch) release has been completed. ' Test Conductor Signature Date i iCAM '81372 - 22 3643

SR-0P-41-X Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 6 ) SOTVice PUBLIC SERVICE COMPANY OF COLORADO 6.0 TEST CONDUCTOR'S REPORT 6.1 Were any procedure changes or deviations made to the test and DCCF/PDR initiated? (Attach copies if applicable) Yes No__. 6.2 Were all steps successfully completed as stated in test? Yes No 6.3 If the answer to 6.2 is NO, notify Department Supervisor and list conditions and/or SSR number (s): 6.4 Test completed except for items noted in 6.3 Test Conductor Date 6.5 Test sheets and data sheets reviewed and approved except for items noted in 6.3 Department Representative Date 7.0 DEPARTMENT SUPERVISOR'S/ TEST CONDUCTOR'S REVIEW (If the answer to 6.2 is YES, sections 7.0 and 8.0 are not applicable go to Section 9.0) 7.1 Does the failure described in 6.3 require any action or impose any limit to operation per the applicable LC0(s)? Yes No N/A 7.2 Applicable LC0(s) ELCO 8.1.3b Action or Limit 7.3 Is the reason test is not being completed at this time due to plant or equipment status? Yes No N/A 7.4 If the answer to 7.3 is YES, list condition (s) and/or SSR number (s): 7.5 Is retest necessary for items listed in 6.3 and/or 7.4? Yes No N/A FOR*.918; 372 22 3643

SR-0P-41-X Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 6 Service PUBLIC SERVICE COMPANY OF COLORADO 7.6 If the answer to 7.5 is YES; list specific section(s) or step (s) to be retested. Dept. Supervisor / Test Conductor Date 8.0 RETEST SECTION (If the answer to 7.5 is NO go to Section 9.0) 8.1 Verify satisfactory retest of section(s) or step (s) listed in 7.6 Retest Conductor Date 8.2 Retest reviewed. Department Representative Date 9.0 APPROVALS 9.1 Test results approved. Satisfactory results confirm compliance with applicable LC0(s). Department Supervisor Date 9.2 Notification of satisfactory test results and test conclusion: Shift Supervisor Date 9.3 Requires Station Manager evaluation: Department Supervisor Date 9.4 Station Manager Date 10.0 DATA SHEETS RECEIVED,_ VERIFIED SECTION 9.0 COMPLETE, AND SURVEILLANCE TEST RECORDS UPDATED. Scheduling Technician Date FORM +91372 22 3643}}

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