ML20052A163

Amends 55 to Licenses DPR-35,revising Tech Specs to Incorporate Limiting Conditions for Operation & Surveillance Requirements of Containment Atmosphere Dilution Sys

ML20052A163
Person / Time
Site:	Pilgrim
Issue date:	03/20/1982
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Boston Edison Co
Shared Package
ML20052A164	List: ML20052A163 ML20052A168
References
DPR-35-A-055 NUDOCS 8204270509
Download: ML20052A163 (6)

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UNITED STATES 2

NUCLEAR REGULATORY COMMISSION a

5 aE WASHINGTON. D. C. 20555

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BOSTON EDISON COMPANY 00CXET NO. 50-293 PILGRIM NUCLEAR POWER STATION

,AfENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-35 l.

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

A.

The application for amendment by Boston Edison Company (the licensee) dated September 30, 1981 complies with the standards and requirements of the Atomic Energy Act' of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance w,ith the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public;

, and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2 Accordingly, the license is amended by changes to the Technical Spec-ifications as indicated in the attachment to this license amendment and paragraph 3.B of Facility Operating License No' OPR-35 is hereby amended to read as follows:

i B.

Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.55, are hereby incorporated in the license. The licensee shall operate the facility in c

accordance with the Technical Specifications.

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2 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION "f f

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Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing

Attachment:

Changes to the Technical Specifications

-Date of Issuance:

March 20, 1982 e

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• w ATTACHMENT TO LICENSE AMENDMENT N0. 55 FACILITY OPERATING LICENSE NO. DPR-35 DOCKET N0'. 50-293 Replace the following pages of-the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are' identified by amendment-number and contain vertical lines indicating the area of change.

Remove Insert 157b 171 171 171a O

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s I,IMITING CONDITIONS FOR OPERATION SURVEILLARCE REQUIREMENTS 3.7.A PRIMARY CONTAINMENT 4.7.A PRIMARY CONTAIh M T t

7. Containment Atmosphere Dilution

7. Containment Atmosphere Dilution

a. Within the 24-hour period

a. The post-LOCA containment after placing the reactor atmosphere dilution system in the Run Mode the Post-shall be functionally LOCA Containment Atmos-tested once per operating phere Dilution System must cycle.

be operable and capable of supplying nitrogen to the containment for atmosphere dilution.

If this speci-fication cannot be met, the system must be restored to an operable condition within 30 days or the reactor must be at least in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b. Within the 24-hour period

b. The level in the liquid N after placing the reactor storage tank shall be re 2 in the Run Mode, the corded weekly.

Nitrogen Storage Tank shall contain a minimum of 1500 gallons of liquid N

• If 2

this specification cannot be met the minimum volume will be restored within 30 days or the reactor must be in at least Hot Shut-down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

c. There are 2 H analyzers

c. The H analyzers shall 2

available to serve the 2

be tested for operability

drywell, once per month and shall be calibrated once per 6 months.

With only 1 H analyzer

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2 operable, reactor oper-ation is allowed for up to 7 days.

If the in-operable analyzer is not made fully operable within I

7 days, the reactor shall

d. Once per month each manual or be in at least Hot Shutdown power operated valve in the within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, CAD system flow path not locked, sealed or otherwise secured in position shall be With no H analyzer per-2 observed and recorded to be able, reactor operation is allowed for up to 48 in its correct position.

hours.

If one of the in-operable analyzers is not made fully operable within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Amendment No. 55 157b l

BASES:

3.7. A & 4.7.A Primary Containment (Cont'd)

The primary containment is normally slightly pressurized during periods of reactor operation.

Hitrogen used for inerting could leak out of the containment but air could not leak -in to increase oxygen concentration.

Once the containment is filled with nitrogen to the required concentra-tion, no moni.toring of oxygen concentration is necessary. However, at least twice a week the oxygen concentration will be determined as added assurance. Mark I Containment Long Term Program testing showed that maintaining a drywell to wetwell pressure differential to keep the sup-pression chamber downcomer legs clear of water significantly reduced suppression chamber post. LOAC hydrodynamic loads. A pressure of 1.17 psid is required to sufficiently clear the water legs of the downtomers without. bubbling nitrogen into the suppression chamber at the 3.00 ft.

downcomer submergence which corresponds to approx. 84,000 ft.3 of water.

Maximum downcomer subme.gence is 3.25 ft. at operating suppression chamber water level. The above pressure differential and submergence number will be used in the Pilgrim I Plant Unique Analysis to be submitted to the NRC.

Post LOCA Atmosehere bilution-In order to ensure that the containment atmosphere remains inerted, i.e.

the oxygen-hydrogen mixture below the flammable limit, the capability to inject nitrogen into the containment after a LOCA is provided. A minimum of 1500 gallons of liquid N2 in the storage tank assures that a three-day supply of N2 for post-LOCA containment inerting is available. Since the inerting makeup system is continually functioning, no periodic testing of the system is required.

The Post-LOCA Containment Atmospheric' Dilution (CAD) System is designed to meet the requirements of AEC Regulatory Guides 1.3,1.7 and 1.29, ASME Section III, Class 2 (except for code stamping) and seismic Class I as defined in the PNPS FSAR Section 12.2.3.5 and Section 2.5.3.

In summary, the limit'ing criteria are:

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**'Am'en'dment No. 55 171 4

t 1.

Maintain hydrogen concentration in the contain-ment during post-LOCA conditions to less than 4%.

2.

Limit the buildup in the containment pressure due to nitrogen addition to less than 28 psig.

3.

Io limi.t the offsite dose due to containment venting (for pressure control) to less than 300 Rem to the thyroid.

By maintaining at least a 3-day supply of N, on site there will be sufficient time after the occurrence of a LOCA for ob tionalnitrogensupplyfromlocalco=mercialsources.yggningaddi-The

. system design contains sufficient redundancy to ensure'its reliabili-ty.

Thus, it is sufficient to test the operability of the whole system once per operating cycle. The H analyzers will provide 2

redundancy for the drywell i.e., there are two H analyzers for the 2

Unit. By permitting reactor operation for 7 days with one of the two H, analyzers inoperable, redundancy of analyzing capability will 5e maintained while not imposing an i==ediate interruption in plant operation. Monthly testing of the analyzers using H2 "i1l be adequate to ensure the system's readiness because of the design.

Since the analyzers are normally not in operation there will be little deterioration due to use.

In order to determine H concentration, the y

analyzers must be warmed up 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> prior to putting into service.

This time frame is acceptable for accident conditions becasue a 4%

H level will not be reached in the drywell until 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> following 2the accident. Due to nitrogen addition, the pressure in the con-tainment after a LOCA will increase with time.

Under the worst expected conditions the containment pressure will reach 28 psig in approximately 45 days.

If and when that pressure is reached, vent-ing from the containment shall be manually initiated per the require-ments of 10CFR50.44. The venting path will be through the Standby Gas Treatment system in order to minim 4ze the off site dose.

(1). As listed in Pilgrim Nuclear Power Station Procedure No. 5.4.6 " Post Accident Venting".

Amendment No. 55 171a k..