ML20133Q233

Amend 91 to License DPR-28,revising Tech Specs to Provide Iodine Spike Limit for Reactor Coolant Concentration & to Limit Opening of Two Purge & Vent Valves to 50 Degrees While Reactor Operating

ML20133Q233
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	10/28/1985
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Vermont Yankee
Shared Package
ML20133Q235	List: ML20133Q233 ML20133Q239
References
DPR-28-A-091 26012, NUDOCS 8511010448
Download: ML20133Q233 (10)

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UNITED 3TATES i

NUCLEAR REGULATORY COMMISSION j

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j WASHINGTON D. C. 20555

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VERMONT YANKEE NUCLEAR POWER CORPORATION DOCKET NO. 50-271 1

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VERMONT YANKEE NUCLEAR POWER STATION a

i AMENDMENT TO FACILITY OPERATING LICENSE i

Amendment No. 91 4

License.No. DPR-28 i

1.

The Nuclear Regulatory Comission (the Comission) has found that:

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The application for amendment by Vermont Yankee Nuclear Power

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A.

Corporation (the licensee) dated January 15, 1985 complies with the 1

i standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations 1,et i

forth in 10 CFR Chapter I; t

i B.

The facility will operate in conformity with the application, the l

provisions of the Act, and the rules and regulations of the j

Comission; i

C.

Thereisreasonableassurance(1)thattheactivitiesauthorized i

by this amendment can be conducted without endangering the health j

and safety of the public, and (ii) that such activities will be conducted in corrpliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comen defense and security or to tie health and safety of the i

public; and 1

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 l

of the Comission's regulations and all applicable requirements have been satisfied.

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1 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-28 is l

hereby amended to read as follows:

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1 fog 10{0 g g g 73 l

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. (2)TechnicalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 91, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION Domenic 8. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance:

October 28,1985 e

ATTACHMENT TO LICENSE AMENDMENT NO. 91 FACILITY OPERATING LICENSE NO. DPR-28 DOCKET NO. 50-271 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.

Pages 106 106a (added) 107 107a (added) 119 135 146 l

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VYNPS i

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3.6 LIMITING CONDITIONS FOR OPERATION 4.6 SURVEILLANCE REQUIREMENTS i

i 3.6 REACTOR COOLANT SYSTEM 4.6 REACTOR COOLANT SYSTEM 1

Specification; i

i A.

Pressure and Temperature Limitations (cont.)

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5.

The reactor vessel irradiation l

surveillance specimens shall be removed j

and examined to determine changes in i

material properties in accordance with the following schedule:

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CAPSULE REMOVAL YEAR i

1 10 f

2 30 f

3 Standby The results shall be used to update i

Figures 3.6.2 and 3.6.3.

The removal l

times shall be referenced to the 3

refueling outage following the year j

specified, referenced to the date of commercial operation.

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B.

Coolant chemistry B.

Coolant Chemistry A sample of reactor coolant shall 1.

a.

During reactor power operation, the 1.

a.

l radiciodine concentration in the be taken at least every 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> j

reactor coolant shall not exceed and analyzed for radioactive 1.1 microcuries of I-131 dose iodines of 1-131 through I-135 equivalent per gram of water, during power operation.

In

' addition, when steem jet air except as altowed in Specification 3.6.B.I.b.

ejector monitors indicate an increase in radioactive gaseous effluents of 25 percent or 5000 uCL/see, whichever is greater.

l A,ena ent so. pl 91 106 i

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VYNPS 3.6 LIMIT 15C COWOITIONS FOR OPERATION a

4.6

$URVEILtJUSCE REQUIREMENTS 3.6 REACTOR COOLANT SYSTER 4.6 REACTOR C00f.4WT SYSTEM i

3.

Coolant Chemistry (cont'd) 3.

Coolant Chemistry (cont'd) 1.

a.

during steady state reactor operation a reactor coolant sample shall be taken and analyzed for r

radioactive iodines.

t.

The radiolodine concentration in b.

An isotopic analysis of a reactor the reactor coolant shall not coolant sample shall be made at l

exceed 1.1 microcuries of 1-131 teast once per month.

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dose equivalent per gram of water, for greater than 24 consecutive hours.

c.

The ratiolodine concentration in c.

Whenever the radiciodine the reactor coolant shall not concentration of prior steady-state exceed 4.0 microcuries of I-131 reactor operation is greater than dose equivalent per gram of water.

0.011 uCL/gm but less than 0.11 pCL/ge, a sample of reactor coolant shall be taken within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the next reactor startup and analyzed for radioactive lodines of 1-131 through 1-135.

e d.

Whenever the radiolodine concentration of prior steady-state reactor operation is greater than 0.11 pCi/gm. a sample of reactor coolant shall be taken prior to the i

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cmndsent No. yf 91 lose l

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VYWPS

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3.6 LIMITING CONDIT105S FOR OPERATION 4.6 SURVEILt.ANCE REQUIREMENTS

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i 3.6 REACTOR COOLANT SYSTER 4.6 REACTOR COOLANT SYSTEM

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3.

Coelaat Chemistry (cant'd) 3.

Coolant Chemistry (cont'd) l j

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d.

next reactor startup and analyzed (cont'd) for radioactive lodines of I-131 j

through 1-135, as well as within 24 I

hours following a reactor startup.

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With the radiolodine concentration I

in the reactor coolant greater than

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1.1 microcuries/ gram dose 4

equivalent 1-131, a sample of

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i reactor coolant shall be taken i

avery 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and analyzed for

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radioactive lodines of I-131 through 1-135, until the specific activity of the reactor coolant is l

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restored below 1.1 microcuries/gran dose equivalent I-131.

1 2.

The reactor coolant water shall not 2.

During startups and at steaming rates i

exceed the following lialts with below 100.000 pounds per hour, a sample

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steaming rates less than 100,000 pounds of reactor coolant shall be taken every per hour except as specified in

." four hours and analyzed for conductivity specification 3.6.3.3:

and chloride content.

Come: activity Sumhoica chloride ion 0.1 ppm t

I 3.

For reactor startups the mentsum value 3.

a.

With steaming rates greater than or for conductivity shall not exceed 10 equal to 100,000 pounds per hour, a unhorca and the monimum value for reactor coolant sample shall be i

chloride ion concentration shall not I

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asee.sment No. 91 107 1

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VYWPS

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3.6 Lin1Tlec CONDIT105S Fet OptEAT105 4.6 SURVEILLANCE REQUIRDIENTS I

I 3.6 REACTOg rawawT SYSTWE 4.6 REACTOR COOtAIFT SYSTEM l

3.

Coelant Cheelstry (cont'd) 3.

Coolant chemistry (cont'd)

I 3.

encoed 0.1 ppe. In the reacter coolant 3.

a.

taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and (cont *d) water for the first 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> af ter (cont'd) when the continuous conductivity j

placing the reactor in the power monitors indicate abnormal operating condition.

conductivity (other than short-teria I

spikes), and analyzed for conductivity and chloride ion content.

b.

When the continuous conductivity monitor is inoperable, a reactor coolant sesyte shall be taken every four hours and analyzed for 1

conductivity and chloride ion content.

4 Except as specified in Specification 3.L.3.3 above, the reactor coolant water shall met, escoed the following limits l

with steeming rates greater than or equal to 100.000 pounds per hours.

f Conductivity 5 uhmo/cm f

Chloride ion 0.5 ppa f

5.

If Specification 3.6.3. Es not met. an i

ecderly shutdown shall be intitiated and l

the reactor shall be in the cale shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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i 107*

Amendment No. 91 m, _ _--m-

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YYNPS 3.6 & 4.6 (cont'd) calculated ca the basis of the radiolodine concentration ilmit of 1.1 uCL of 1-131 dose equivalent per gram of water, atmospheric dif fusion from an equivalent elevated release of 10 meters at the nearest site boundary (190 m) for a XIQ = 3.9 x 10-3 see/m3 (Pasquill D and 0.33 m/see equivalent), and a steam line isolation votre closure time of five seconds with a steam / water mass release of 30.000 pounds.

The iodine spike 11 alt of four (4) microcuries of I-131 dose equivalent per gram of water provides an iodine peak or spike limit for the reactor coolant concentration to assure that the radiological consequences of a postulate LOCA are within 10CyR Part 100 dose guidelines.

The reactor coolant sample will be used to assure that the limit of Specification 3.6.B.1 is not exceeded. The radiciodine concentestion would not be expected to change rapidly during steady-state operation over a period of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />. In addition, the trend of the radioactive gaseous effluents, which is continuously monitored, is a good indicator of the trend of the radiolodine concentration in the reactor coolant. When a significant increase in radioactive gaseous effluents is indicated, as specified, an additional reactor coolant sample shall be taken and analyzed for radioactive lodine.

Whenever an isotopic analysis is performed, a reasosable ef fort will be made to determine a significant I

percentage of those contributors representing the total radioactivity in the reactor coolant sample. Usually at least 80 percent of the total gamma radioactivity can be identified by the isotopic analysis.

It has been observed that radiolodine concentration can change rapidly in the reactor coolant during transient reactor operations, such as reactor shutdown, reactor power changes, and reactor startup if f ailed fuel is present. As specified, additional reactor coolant samples shall be taken and analyzed for reactor operations in which steady-state radiciodine concentrations in the reactor coolant indicate various levels of lodine releases frem the fuel. Since the radiniodine concentration in the reactor coolant is not continuously measured, reactor coolant sampling would be inef fective as a means to rapidly detect gross fuel element f ailures. However, some capability,to detect gross fuel element fattures is inherent in the radiation monitors in the off-gas system on the main steam line.

l Materials in the primary system are primarily 304 stainless steel and Zircoloy. The reactor water chemistry limits are established to prevent damage to these materials.

The, limit placed on chloride concentration is to l

prevent stress corrosion cracking of the stainless steel.

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/cen &ent 33. 91 g19

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VYNPS TABLE 4.7.2.s e

PRIMARY CONTAIMMENT ISOLATION VALVES VALVES SUBJECT TO TYPE C LEAKAGE TESTS Number of Power Maximum Action on 1

Operated Valves _

Operating Normal Initiating i

Isolatloa I

Valve Identification Inboard outboard Time (sec) Position signa!

Croup 1

noin Steen Line leolation (2-80A D & 2-86A. D) 4 4

5(Note 2) Open CC l

1 natn Steen Line Drain (2-74 2-77) 1 2

35 Closed SC 1

Recirculation Loop Snapte Line (2-39, 2-40) 1 1

5 Closed SC 2

25 Closed SC 2

RHE Discharge to Redweste (10-57, 10-66) 2 20 Open CC l

2 Drywell Floor Drain (20-82. 20-83) 1 2

Drywell Igulpment Drain (20-94 20-95) 2 20 open CC 1

10 Closed SC 3

Drywell Air Purge Inlet (16-19-9) 1 10 Open CC 3

Drywell Air Purge Inlet (16-19-8) 1 10 Closed

• SC

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Drywell Purge & Vent Outlet (16-19-7A) 1 10 Closed SC 3

Drywell Purge & Vent Outlet Bypass (16-19-6 A) 1 10 Closed

• SC l

3 Drywell & Suppression Chamber Main Exhaust (16-19-7) 1 10 Closed SC 3

Surpression Chamber Purge Supply (16-19-10) 1 10 Closed SC 3

Suppresalon Chamber Purge & Vent Outist (16-19-75) 1 10 Open CC 3

SuFFression Chamber Purge & Vent Outlet Bypass (16-19-65) 1 10 Open CC 3

Exhaust to Standby Cas Treateent System (16-19-6)

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10 Open CC f

3 containment Purge Supply (16-19-23) 3 Containment Purge Makeup (16-20-20, 16-20-22A, 16-20-228) 3 FA Closed SC I

1 25 Open cc I

5 Reactor cleanup System (12-15, 12-18) 1 45 Open GC 5

Reactor Cleanup System (12-68)

'1 1

55 open cC 6

NPCI (23-15, 23-16)

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20 Open cc i

6 RCIC (13-15. 13-16) 2 NA Closed SC Primary / Secondary Vacuum Relief (16-19-11A. 16-19-118) 2 NA Closed Process Primary / Secondary Vacuum Relief (16-19-12A 16-19-128) j NA open Process Control Rod Hydraulle Return Check Valve (3-181) 4 5

Open CC 3

C'ontainment Air Step 11ng (VC 23. VC 26. 109-76A&B) 0 or less.

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• Valves 16-19-7 and 16-19-7A shall have stops installed to limit valve opening to 50 135 Amendment No. se, es. J4' 91 i

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i4.7.D. Primary containment Isolation valves Those large pipes comprising a portion of the reactor coolant system whose failure could result in uncovering the reactor core are supplied with automatic isolation valves (except those lines needed for emergency core cooling system operation or containment cooling). The closure times specifLed herein are adequate to prevent loss of more cooling from the circumferential rupture of any of these lines outside the containment than from a steam line rupture. There, this isolation valve closure time is suff telent to prevent uncovering the core.

purge and went valve testing performed by Allis-Chalmers has demonstrated that all butterfly purge and vent valves l

installed at Vermont Yankee can close from full open conditions at design basis containment pressure. However, as an j

additional conservative measure. Limit stops have been added to valves 16-19-7/7A, limiting the opening of these open while operating, as requested by unc in their letter of May 22, 1984 (NVY 84-108) j valves to 508 i

In order to assure that the doses that may result from a steam line break do not exceed the 10CFR100 guidelines, it is i

necessary that no fuel rod perforation resulting from the accident occur prior to closure of the main steam line

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isolation valves. Analyses indicate the fuel rod cladding perforations would be evolded for the main steam valve 7

closure times, including instrument delay, as long as 10.5 seconds. The test closure time limit of five seconds for j,

these main steen isolation valves provides suffLeient margin to assure that cladding perforations are avoided and 10CFt100 timits are not exceeded. Redundant valves in each line insure that Laolation will be effected applying the i

single failure criteria.

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j The main steam line isolation valves are functionally tested on a more frequent interval to establish a high degree of l

reliability.

i The containment is penetrated by a large number of small diameter instrument. lines. A program for periodic testing

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and examination of the flow check valves in these lines is perfot1ned.sistler to that described in Amendment No. 23, Millstone Unit 1. Docket 50-245.

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l Amendment No. 91

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