ML19351D619

Application for Amend to Provisional License DPR-16,App a, Changing Tech Specs Re Iodine Removal Efficiency & Air Filter Flow Distribution Testing.Certificate of Svc Encl

ML19351D619
Person / Time
Site:	Oyster Creek
Issue date:	10/06/1980
From:	Finfrock I JERSEY CENTRAL POWER & LIGHT CO.
To:	Office of Nuclear Reactor Regulation
References
EAJL-80-124, NUDOCS 8010140244
Download: ML19351D619 (9)

Text

. . . - - -.. _- - .- . . . - . - . _ . - - . _ _ -- . - _ . . . . . . . - _ _ _

i l

I N

~

i l

l. rW ,. W.,2' f

, Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road l C' -

h6 1 e Momstown. New Jersey 07960 (201)455-8200 I

EAJL-80-124 October 6, 1980 i >

l Director Nuclear Reactor Regulation l Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request No. 82 In accordance with 10 CFR 50.59 and 10 CFR 50.90, Jersey Central Power &

Light Company, owner and operator of the Oyster Creek Nuclear Generating Station, Provisional Operating License No. DPR-16, request changes to Appendix A of that iIcense.

The subject Technical Specification Change Request involves Sections j 4. 5. K .1.a ( 2 ) and 4.5.K.1.a(3) of the Technical Specifications. Section 4.5.K . I . a( 2 ) shall be revised such that radioactive methyl iodine removal efficiency will be tested in accordance with ASTM D 3803-79 instead of ANSI N510. In addition, the Standby Gas Treatment System air filter flow distribution I test shall be p er f ormed in accordance with ANSI N510 therefore, Section l .4.5.K.1.a(3) wili be eliminated.

The. Technical Specification Change Request has been reviewed and l approved by the Station Superintendent, the Plant Operations Review Committee, and an Independent Safety Review Group in accordance with Section 6.5 of the Oyster Creek Technical Specifications.

We have determined that this submittal is Class ill per 10 CFR 170.22 and have enclosed a check for $4,000 pursuant to that section.

Very truly yours,

&ff , N >

Ivan 3. Finfr ek, r.

Vice President t

t i

pftra ( 2 ., ,

8 010140 M Jersey Central Power & Light Company is a Member of the General Pubhc (Jt.ptjes System __

JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GE"? RATING STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 Technical Specification Change Request No. 82 Docket No. 50-219 Applicant subnits, by this Technical Specification Change Request No. 82 to the Oyster Creek Nuclear Generating Station Technical Specifications, a change to Specification 4.5.K.1.a.

JERSEY CENTRAL WER & LIGHT COMPANY BY *- ))j]) // g_ ] _

ice res ent

' STATE & NEW JERSEY COUNTY T MORRIS Sworn and subscribed to before me this $ day of Oc)+h,1980.

1 Da~;12 C. ALah-Notary Public DAVID C. SHADLE NOTARY PUBtlC 0F NEW JEarry My Commission Expires Oct. 3,1953 l

l l

l l

l l

l i

l

JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATIfG STATION PROVISIONAL OPERATING LICENSE NO. DPR-16 Technical Specification Change Request No. 82 Docket No. 50-219 Applicant subnits, by this Technical Specification Change Request No. 82 to the Oyster Creek Nuclear Generating Station Technical Specifications, a change to Specification 4.5.K.1.a.

JERSEY CCNTRAL POW & LIGHT COMPANY BY: __/ gjj q Vice Pr id

/

STATE OF NEW JERSEY COUNTY & MORRIS Sworn and subscribed to before me this ($ N day of 04~ ,1980.

t lS C.b Y o Notary Public

~

l DAVID C. SHADLE NOTARY FUEL!C 0F Ir!/ mrl My Commissica Expires Oct. 3,1933 l l

l

• Jersey Central Power & Light Company

. i (4" ( Madison Avenue at Punch Bowl Acad Mornstown. New Jersey 07960 (201)455-8200 October 6, 1980 The !!cnorable llenry Von Spreckelsen Mayor of Lacey Township P. O. Cox 475 Forked River, New Jersey 08731

Dear Mayor Von Spreckelsen:

Enclosed herewith is one copy of Technical Specification Change Request '.o. 82 for the Oyster Creek Nuc1 car Generating Station Technical Specifications.

These documents were filed with the U.S. Nuclear Regulatory Commission on October 6 , 1980.

Very tnily yours, 08 5 , .,/)/ O Ivan R. Finf ek r.

Vice Presi t -

la Enclosures

! Jersey Central Power & Light Company is a Member of the General Pubhc Utilities System

V 'W CENTRAL POWER & LIGHT COMPANY L DJ CREEK NUCLEAR GENERATING STATION (DOCKET NO. 50-219) s PROVISIONAL OPERATING LICENSE DPR-16 Applicant hereby requests the Commission to chango Appendix A'of the

. above captioned license as follows:

1. Section to be changed:

2 Section 4.5.K.1.a j 2. Extent of Changes 3

a) Specification 4.5.K.1.a(2). Perform testing in accordance with ASTM D 3803-79 rather than ANSI N510-79.

b) Eliminate Specificat ion 4.5.K.l.a(3).

3. Change Requested:

The requested cha.ye is on the attacheu sevised Technical Specification pages 4.5-5a, 4.5-5b, 4.5.9b, and 4.5.9c.

4. Discussion:

Technical Specification 4.5.K.l.a.(2) requires that laboratory analysis be performed on carbon samples removed from the Standby Gas Treatment System, in accordance with ANSI N510-1975 (130

• C, 95% relative humidity), in order to determine the systems radioactive methyl iodine removal efficiency. ASTM D 3803-79 (Radiciodine Testing of Nuclear-Grade Gas-Phase Absorbents) provides for testing at 30

• C, 95% relative humidity. The costs associated with performing the test at 30* C rather tnan 130 C are lower. Therefore, the purpose of the subject Technical Specification Change Request is to allow testing to be performed in accordance with ASTM D 3803-79 rather than ANSI N510-1975.

Technical Specification 4.5.K.l.a.(3) requires that an air flow distribution test be performed at least once every 18 months on the HEPA and charcoal filters of the Standby Gas Treatment System. In that it is impractical to perform this test, and in light of the fact that the Nuclear Regulatory

Commmission no longer recuires its inclusion in the Technical Specifications, it is the .ourpose of this Technical Specification Change Request to eliminate the subject specification. The Standby Gas Treatment System filters shall be tested in accor3ance with ANSI N510.

- - , - -v,r, re-, n ,

i I 4.5-Sa l

l pressure of not less than 1.0 psi, the differential pressure l' decay rate shall not exceed the equivalent of air flow through a 2-inch orifice.

J. Reactor Building i

1. Secondary containment capability tests shall be conducted after isolating the reactor building and placing either Standby Gas Treatment System filter train in operation.

2. 'Ibe tests shall be performed at least once per operating cycle and shall demonstrate the capability to maintain a 1/4 inch of water vacuum under calm wind conditions with a Standby Gas Treatment System Filter train flow rate of not more than 4000 cfm.

3. A secondary containment capability test snall be conducted at each refueling outage prior to refueling.

4. The results of the secondary containment capability tests shall be I in the subject of a sumary technical report which can be included in the reports specified in Section 6.

K. Standby Gas Treatment System

1. The capability of each Standby Gas Treatment System circuit shall to demonstrated by:

i

a. At least once per 18 .nonths, after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of ,

l operation, and following significant pa!nting, fire, or chemical '

release in the reactor building during operation of the Standby Gas Treatment System by verifying that:

(1) The enarcoal absorbers remover 99% of a halogenated hydrocarbon refrigerant test gas and the HEPA filters remove 2 99% of the DOP in a cold DOP test when tested in accordance with ANSI N510-1975.

(2)- Results of laboratory carbon sample analysis show a 90%

radioactive methyl iodine removal efficiency when tested in accordance with ASTM D 3803-79' ( 30* C, 95% relative

. humidity) .

b. At least once per 18 months by demonstrating:

- - ,,_.~, .- .- -. -. , . - . - , . - _ . - - . , , - - . - - . -

4. 5 -5b (1) Tnat tne pressure drop across a IIcPA filter is equal to or less tnan tne maximum allowable pressure drop indicated in Figure 4.5.1.

(2) Tne inlet neater is capable of at Icast 10.9 Kii input.

(3) Operation witn a total tiow within 10% of design flow.

c. At least once per 30 days on a STACGERED TEST BASIS by operating eacn circuit for a minimum of 10 nours.

a. Anytime the ficPA filter canK or tnc cnarcoal adsorcers nave oeen partially or completely replaced, the test for 4.5.K.1.a will be performed prior to returning tne system to OPERABLE alAIU5.

e. Automatic initiation of escu circuit every 18 montns.

l l

l 1

l l

6 l

4.5.9b of the system. Although this is basically a leak test, since the filters have charcoal of known efficiency and holding capacity for elemental iodine and/or methyl iodide, the test also gives an indication of the relative officiencf of the installed system.

The test procedure is an adaptation of test procedures developed at the Savannah River Laboratory which were described in the Ninth AEC Air Cleaning Conference.*

liigh efficiency particulate filters are installed before and after the charcoal filters to minimize potential release of particulates to the environment and to prevent clogging of the iodine filters.

An efficiency of 999, is adequate to retain particulates that may be released to the reactor building following an accident. This will be demonstrated by testing with DOP at testing medium.

If laboratory tests for the adsorber material in one circuit of the Standby Gas Treatment System are ur acceptable, all adsorber material in that circuit shall be replaced vith adsorbent qualified according to Regulatory Guide 1.52. Any llEPA filters found defective shall '

be replaced with those qualified Nith Regulatory Position C.3.d of Regulatory Guide 1.52. IIEPA and charcoal filter air flow distribution tests shall be conducted,. in accordance with ANSI N510-1975, when the filters are initially installed and whenever work on the system may affect distribution.

The snubber inspection frequency is based upon maintaining a constant level of snubber protection. Thus, the required inspection interval varies inversely with the observed snubber failures. The number of i inoperabic snubbers found during a required inspection determines the time interval for the next required inspection. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection, llowever, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25*>) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

l I Experience at operating facilities has shown that the required surveillance program should assure an acceptable level of snubber performance provided that the seal materials are compatibic with l the operating environment.

l Snubbers containing seal material which has not been demonstrated l

by operating experience, lab tests or analysis to be compatible l

with the operating environment should be inspected more frequently

! (every month) until material compatibility is confirmed or an

! appropriate changeout is completed.

To further increase the assurance of snubber reliability, functional tests should be performed once each refueling cycle. These tests will include stroking of the snubbers to verify proper piston movement, lock-up and bleed. Ten percent or ten snubbers, whichever is less, represents an adequ?.te sample for such tests. Observed failures of these samples should require testing of additional units. Snubbers in high radiation areas or those especially difficult to remove (see Table 3.5.1) need not be selected for functional tests provided operabilitv was previously verified.

• 4.5.9c Snubbers of rated capacity greater than 50,000 lb. are exempt from the functional testing requirements because of the im-practicability of testing such large units.

• D. R. Muhbaier, "In Place Nondestructive Leak Test for Iodine Absorbers", Proceedings of the Ninth AEC Air Cleaning Conference, USAEC Report CONF-660904, 1966.

1 T

1 i

1 d

4 l

l l

. - . ._