ML20206K480

From kanterella
Jump to navigation Jump to search
Describes Actions Taken to Control Release of Airborne Effluents to Alap.Leaks in Augmented Offgas Sys Located & Corrected & High Efficiency Filters Installed in Condenser Compartment Ventilation Sys Recirculation Coolers
ML20206K480
Person / Time
Site: Pilgrim, 05000000
Issue date: 05/02/1975
From: James Smith
BOSTON EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20204E974 List:
References
FOIA-86-58 NUDOCS 8606300102
Download: ML20206K480 (2)


Text

, ..o ,,

e cr , , Ar

- niimm - .

pk %M w PILORIM NUCLEAR POWLR STATION Rr0 21 Rocky Hitt Romo RLv h8 0 0 T H. M45MACHusttin 0?360 g Hay 2, 1975 Director, Inspection and Enforcement Region I phg U.S. Nuclear Regulatory Commission

. 631 Park Avenue King of Prussia, Pennsylvania 19406 .

Inforination Report Docket Number 50-293 License DPR-35. Amendment No. 8

Dear Sir:

We wish to advise you of actions taken at Pilgrim Nuclear Power Station to con-trol the release of airborne effluents to as low as practical.

Based on observations of an increasing trend in the daily gaseous relcaec rate of halogens and particulates with half lives greater than eight days, Pilgrim Station was shutdown on April 15, 1975 to locate and repair steam Icaks in the main condenser compartment'and to perform other minor maintenance activities as required. Leaks in the Augmented Off-Cas System and other sources of radio-active gases, which contributed to the* airborne effluent release rate, were located and corrective action taken as necessary. In addition, high efficiency filters were installed in the condenser compartment ventilation system recir-culation coolers. ,

During this shutdown period, numerous procedural innovations were implemented l

in an attempt to reduce reactor coolant activity. These included variations

-) of the reactor coolant temperature and operation of the reactor water cleanup system at its maximum capacity. Also, all of the general operating procedures for station startup and shutdown were revised to include the latest aspects ,

required to control the release of radioactive gases.

1

! The' station was returned to power operation on April 21. Numerous inspections were performed during the startup activities to assure that sources of, air-borne releases were located and corrected. An inspection of the high pressure turbine revealed that a small leak existed in the gland steam scaling system J

exhaust header. Individual system operations were coordinated or rescheduled, during the startup, to minimize the release of airborne effluents.

on April 22, at 2139 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.138895e-4 months <br />, the unit was removed from service due to indica-4 tions (tail pipe temperature of approximately 2200F) of steam leakage through the pilot seat of the "A" main steam relief / safety valvo. The "A" relief /

safety valve was replaced with a spara on April 23, 1975.

While the station was shutdown additional charcoal filters were installed in j portions of the turbine building and radwaste building exhaust ventilation j ducts. The installation of these filters was recommended by our consultants, Nuclear Safety Associates and Nuclear Environmental Services who have been j consigned to locate.and recommend measures to control our release of airborne j effluents. -

8606300102 860613 PDR FOIA b/6 BURNSTEIB6-58 PDR m.

Directer, Inspection cnd Enfarcement 5/2/75

. .. d, .

, , 1 . . .

  • The reactor was restarted on April 27, in preparation for returning the statien to power operation. During the subsequent startup activitics a routino dryucil '

inspection was made and secam was observed to be Icaking from the tent plur, on "B" main steam relf.cf/ safety valve. To repair this, the reactor was placed in the cold shutdown condition, and the. valve was replaced with another spare .

valve. During this outage, some carbon filters were installed in the condenser l compartment recirculating fans.

During the period of April 22 to April 29, while these maintenance activities l Vere being performed on the primary system, an analysis of the charcoal and l particulate filters from the reactor building vont and the main stack indicated that a release of .0724 curies of halogens and particulates with half lives i greater than eight days had occurred. ,

The station was returned to power operation at 2151 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.184555e-4 months <br /> on April 29, 1975.

During' the startup, both "A" and "B" main steam relief / safety valves ucre satisfactorily tested by remote mancally opening the valves. Also, the gland scalin;; system operating pressure (vacuum) uss increased to control this leakage a- to correct for a possible deterioration of the high pressure turbine seaa.

Additional measures being taken to control radioactive airborne emissions from the building vent include: -

1. Proposed Technical Specification changes were submitted to the NRC on April 2, 1975. These changes would climinate the requirement to report our rather insignificant releases as abnormal occurrences.
2. Procedures to chemically control certain airborne emissions are being ,

investigated.

3. Modifications to the raduast.e ventilation system to provide filtration and better air balance are being investigated.

It is our opinion that these actions are responsive to the requirements to maintain the release of airborne effluents as low as practical. If you have further question,s on this subject, please contact us.

Respectfully submitted,

/

f./ " h \

1. A. Smith
  • Pilgrim Division Head
  • Nuclear Operations a

WP b

d 4 =

\ *

.I

,4 *!. .

DAT{ p' 7 8  %

p Action Cont rol Form Report:. of occurrences

! . Action by Records and Pfles (telegrans or fa mimile transmir.n f ons only) l 1.

Complete reproduction of 15 copier. (9 copits for Telephone Reports) l 2.

Deternine RO:I internal distribution from the latest RO:I assignments list (enter names below) *

a. M o b Brancl Ch f Project (1 copy)Inspector (5 copies) plus senior (1 copy) and
b. Director's Office (1 copy) c.

Records and Files (originaljplus 6 copics for 'xternal distribution)

3. Facility Nane (enter her<.) : _ b.dh b. .

M: t ,-- /

4.

Determine license or docket number: 50- 29 k OccurrenceNo:.._j21/c [

5.

Iland carry copies of the report to the distribution determined in 1[m #

A.2 above; hand carry this form to the Project Inspector.

B.

Action btProject Inspector (all_ reportr of occ rrencos) 1.

Verify License or Docket Number, itcu A.4 above (check here) 2.

Determine a !!IS-Name for this occurrence: Tok me, ke feaco TederwikoM 3.

Determine applicabic regulation under which attached report has made (check one); ident10if CIky tottached 20.402; report and any follow-up repor ts expec ted (enter da t Immid. 30 day, 10 CFR 20.403(a); Immed.

othet

.,30 day, other 10 CFR 20.403(b);__ 24 hr, 10 CFR 20.405; 30 day, other 30 day, other 10 CFR 50.55(e); _ 30 day, 10 CFR 50.71; 24 hr, __other 10 CFR 70.52; 10 day, other Prompt. other 10 CFR 73.42(b); Immed .

Other 15 day, other First, Second

4. other Identify if any previous reports were made on this occurrence, telephone, t elecommunica t ions , letter. /.

5.

Designate R&Ep Brcnch (if any) to receive 3 extra copies of report j M&PP I i

6. No PDR distribution i 1
7. Your name, if not shown in item A.2.a above:
8. lland carry this form to Records and Files.

9.

The report constitutes both a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 10 day notification:

No C. _ Action by Records and Files Yes

(} -

1.

Complete standard transmittals (consider item B 9 above) and prepare for mailing.

SA!!E DAY !!AILIMG IS REQUIRED. (check here)

. 2.

Enter (checkdata here)from this form (items A4, B2, B3 Into the occurrence report file 3.

File this form in ACF c ronological file. t reports only). '

(telegram, facsimile, or telephone RO: 1 Tom 39 (revise,1)

June 74 C,- l l

""" Edison omn (

o PILGRIM NUCLcAR POWcR G T ATIO N Nr0 M1 ROCKY HIL L ROAD PL YMollTH. M A51.s ACHtJGETTH Oc 360 May 2, 1975 Director, Inspection and Enforcement Region I U.S.1:uclear Regulatory Conaission 631 Park Avenue King of Prussia, Pennsylvania 19406 i Information Report Docket thuaber 50-293 Licence DPR-35, Amandment No. 8 e

Dear Sir:

Uc uish to advise you of actions taken at Pilgria Uucicar Power Station to con-trol the relcase of airborne effluents to as low as practical.

Based on observations of an increasing trend in the daily gaseous release rate of halogen *: and particulates uith half liven greater than eight days, Pilgrim Station was shutdown on April 15, 1975 to locate cud repair steam Icaks in the main condenser compartrnent and to perform other itinor maintenance activitics as required. Looks in the Au;,mented Off-Cau System and other sources of radio-active gases, which contributed to the airborne effluent release rate, were located and corrective action taken as necessary. In addition, high efficiency filters ucre installed in the condenser compartment ventilation system recir-culation coolers.

During this shutdoun period, nunerous procedural innovations ucre fraplemented in en attempt to reduce reactor coolant activity. '1hese included variations of the reactor coolant temperature and operatica of the reactor water cicanup system at its maximrm capacity. Also, all of the general operating procedures for station startup and chutdeun ucre revised to include the Intcut aspects required to control the release of radioactive gases.

The etntion was returned to power operr. tion on April 21. Numerous inspections ucre perforr'ed during the att.rtup activitics to Oscure that :,carces of air-borne relensco vere located and corrected. An inspection of the high precourc turbine revealed that a arr.11 leak exirted in the glend secrm coaling system exhauut header. Individual system operations ucre coordinated or rescheduled, during the startup, to minimize the release of airborne effluents.

On April 22, at 2139 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.138895e-4 months <br />, the ' unit uns removed frca cervice due to indica-tions (tail pipe temperature of apprm:imately 2200r) of utcom Icakage through the pilot scot of the "A" main steam relief / safety valve. The "A" relief /

safety valve was replaced uith a aparc on April 23, 1975.

While t.he station was chutdoun additional charecal filters were installed in portions of the turbine building and raduaste building exhaust ventilation ducts. The installation of these filters uns recormended by our consultants, Nuclear Safety Associates and tincicar Environmental Services uho have been I consigned to locate and recocaond measuren to control our relense of airborne effluenb,.

6. . . i ;b Y; % l

LiUrecto6 Inspection and Enforcement ' "

5/2/75

- (

The reactor was restarted on April 27, in preparation for returning the station

.to power operation. During the subsequent startup activitics a routine drywell inspection was made and steam was observed to be Icaking from the test plug on "B" main steam relief / safety valve. To repair this, the reactor was placed in the cold shutdown conditica, and the valve was replaced with another spare valve. During this outage, sor.:e carbon filters were installed in the condenser compartment recirculating fans.

During the period of April 22 to April 29, uhile these maintenance activitics were being performed on the primary system, an analysis of the charcoal and particulate filters from the reactor building vent and the main stack indicated that a release of .0724 curies of halogens and particulaces with half lives greater than eight days had occurred. ,

The stetion uas returned to power operation at 2151 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.184555e-4 months <br /> on April 29, 1975.

During the startup, both "A" and "B" inin steam relief / safety valves were satisfactorily tested by ter ote manually opening the valves. Also, the gland.

scaling systen operating pressure (vacuum) was increased to control this leahage and to correct for a possibic deterioration of the high pressure turbine scals. -'

Additinaal measures being taken to control radioactive airborno emissions from the building vent include:

1. Proposed Technical Specification changes ucre submf tecd to the URC on April 2, 1975. These changes would clirainate the requirenent to report '

our rather insignificant relcanes as abnormal occurrences.

2. Procedures to chemically control certain airborne emissions are being investlncted.
3. 11edificatican to the raduaste ventilation syatem to provide flitration and better air holance arc being investigated.

It is our opinim that these actions are responsive to the requirements to naintain the r<1u .c of airLorne effluents as low as practical. If you have further questicas en this subject, picase contact us. '

Respectfully submitted,

[ r

/,

[J. A. Sr.:ith PilgrLa Division 11 cad Nuclear operations s