ML20134M199

Summary of 850808 Meeting W/Util in Bethesda,Md Re Revised post-accident Sampling Capability Presentation

ML20134M199
Person / Time
Site:	Calvert Cliffs
Issue date:	08/26/1985
From:	Jaffe D Office of Nuclear Reactor Regulation
To:	Butcher E Office of Nuclear Reactor Regulation
References
NUDOCS 8509040007
Download: ML20134M199 (9)

Text

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Docket Nos. 50-317 August 26, 1985 and 50-318 MEMORANDUM FOR: Edward J. Butcher, Acting Chief Operating Reactors Branch No. 3 Division of Licensing &

FROM: David H. Jaffe,~ Project Manager Operating Reactors Branch No. 3 Division of Licensing

SUMMARY

OF AUGUST 8, 1985 MEETING WITH BALTIM0RE GAS AND ELECTRIC COMPANY (BG&E) CONCERNING POST-ACCIDENT SAMPLING (PASS) AT CALVERT CLIFFS On August 8, 1985, representatives of BG&E and the NRC staff met in Room P-422 of the Phillips Building in Bethesda, Maryland. The purpose of the meeting was to discuss the PASS system for Calvert Cliffs Units 1 and 2. A list of attendees is shown in Enclosure 1.

BG&E indicated their desire to abandon the inline, PASS analysis capability.

The modified PASS capability would consist of obtaining a diluted sample and using the on-site laboratory facilities to perform the necessary analysis.

No undiluted samp.ing capability was proposed by BG&E.

The licensee made a presentation to describe the way in which BG&E's revised PASS capability would conform to the NRC's criteria present in its letter to BG&E dated June 30, 1982. A summary of this presentation is shown in Enclosure 2.

At the conclusion of the meeting, it was agreed that the licensee would make a formal PASS submittal including an application for license amendment. The NRC staff agreed to inform BG&E regarding the need for PASS via an undiluted sample.

David H. Jaffe, Project Manager Operating Reactors Branch No. 3 Division of Licensing I 1

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Mr. A. E. Lundvall, Jr.

Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant cc:

Mr. William T. Bowen, President Regional Administrator, Region I Calvert County Board of U.S. Nuclear Regulatory Commission Connissioners Office of Executive Director Prince Frederick, Maryland 20768 for Operations 631 Park Avenue D. A. Brune, Esq. King of Prussia, Pennysivania 19406 General Counsel Baltimore Gas and Electric Company Mr. Charles B. Brinkman P. O. Box 1475 Manager - Washington Nuclear Operations Baltimore, Maryland 21203 Combustion Engineering, Inc.

7910 Woodmont Avenue George F. Trowbridge, Esq. Bethesda, Maryland 20814 Shaw, Pittman, Potts and Trowbridge 1800 M Street, NW Mr. J. A. Tiernan, Manager Washington, DC 20036 Nuclear Power Department Calvert Cliffs Nuclear Power Plant Mr. R. C. L. Olson, Principal Engineer Maryland Routes 2 and 4 Nuclear Licensing Analysis Unit Lusby, Maryland 20657 Baltimore Gas and Electric Company Room 922 - G&E Building Mr. R. E. Denton, General Supervisor P. O. Box 1475 Training and Technical Services Baltimore, Maryland 21203 Calvert Cliffs Nuclear Power Plant Maryland Routes 2 and 4 Lusby, Maryland 20657 Resident Reactor Inspector c/o U.S. Nuclear Regulatory Commission Combustion Engineering, Inc.

P. O. Box 437 -

ATTN: Mr. R. R. Mills, Manager Lusby, Maryland 20657 Engineering Services P. O. Box 500 Mr. Leon B. Russell Windsor, Connecticut 06095 Plant Superintendent Calvert Cliffs Nuclear Power Plant Department of Natural Resources Maryland Routes 2 and 4 Energy Administration, Power Plant Lusby, Maryland 20657 Siting Program ATTN: Mr. T. Magette Bechtel Power Corporation Tawes State Office Building ATTN: Mr. J. C. Ventura Annapolis, Maryland 21204 Calvert Cliffs Project Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 Mr. R. M. Douglass, Manager Quality Assurance Department Baltimore Gas and Electric Company Fort Smallwood Road Complex P. O. Box 1475 Baltimore, Maryland 21203

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ENCLOSURE 1 3

Attendance List i For meeting with Baltimore Gas and Electric Company August 8, 1985 Post-Accident Sampling at Calvert Cliffs Name Organization D. Jaffe NRR/DL/0RB#3 F. Witt NRR/DE/CHEB J. Wing NRR/DE/CHEB J. White NRR/ Region I

V. Benaroya NRR/DE/CHEB BG8E P. Crinigan G. Wolf L. Salyards E

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ENCIDSURE 2 NUREG-0737 CRITERIA j

CRITERIA RESPONSE (1) The licensee shall have the capability (1) The time required for sampling and  !

to promptly obtain reactor coolant analysis of reactor coolant and samples and containment atmosphere containment atmosphere samples will samples. The combined time allotted be:

for sampling and analysis should be three hours or less from the time a RCS PASS:

decision is made to take a sample.

Technician briefing / dress 40 min.

PASS preparation 30 min.

Purge time 20 min.

Analysis 30 min.

TOTAL: 120 min.

Containment Atmosphere:

Technielan briefing / dress 40 min.

' Preparation 10 min.

Purge time 10 min.

Analysis 20 min.

TOTAL: 80 min.

(2) Th licensee' shall establish an onsite radiological and chemical analysis (2) a. An aliquot of the diluted sample shall be diluted further if necessary, capability to provide, within three-hour and a gamma spectrum shall be time frame established above, conducted on this by use of the quantification of the following: chemical laboratory's gamma

, analysis equipment. The radio-

. a. Certain radionuclides in the nuclide analysis of the containment reactor coolant and containment atmosphere shall be conducted by atmosphere that may be indicators obtaining a syringe sample of the of the degree of core damage (e.g., containment atmosphere and ana-noble gases; todines and cesiums, lyzing an aliquot of this mixture on h and non-volatile isotopes); the chemical laboratory's gamma analysis equipment.

b. Hydrogen levels in the con tainment atmosphere; b. Hydrogen levels in the containment

c. atmosphere shall be determined by Dissolved gases (e.g., H2 ), chloride the use of an on-line hydrogen (time allotted for analysis subject analyzer.

i to discussion below), and boron concentration of liquids, c. Dissolved gases can be obtained from the RCS PASS. The dissolved gases are stripped from the liquid and a sample of this can be obtained by means of a syringe. This sample can then be injected into the gas partioner and gas chromatograph

het NUREG-0737 PAGE 2 4

CRITERIA RESPONSE

d. Alternatively, have inline for hydrogen and oxygen analysis. 1 monitoring capabilities to perform The concentration of these gases in all or part of the above analyses. the liquid can then be obtained via

established calculational methods.

3 The chloride analysis can be i obtained by means of a Dionex lon l chromatograph. Since minimum sensitivity of this is 2 - 5 ppb, an analysis of this can be done with a minimum dilution of 30:1 to meet 150 ppb criteria. Since the i minimum boron shutdown margin is 350 ppm, a 30:1 dilution of the sample can also be performed.

Established procedures can meet .

this sensitivity.

(3) Reactor coolant and containment (3) The PASS skid will not require the use atmosphere sampling during post of an isolated auxiliary system as accident conditions shall not require an described in our earlier submittal.

) isolated auxiliary system (e.g., the j letown system, reactor water cleanup j system (RWCUS) to be placed in operation in order to use sampling l system.

i (4) Pressurized reactor coolant snmples (4) This Criterion is satisfied by the

are n'ot required if the licenne can explanation given in 2(C).

quantify the amount of dissolved gases

! with unpressurized reactor coolant samples. The measurement of either tot::1 dissolved gases or H2 gas in reactor coolant samples is considered adequate. Measuring the O2 concentration is recommended, but is not mandatory.

(5) The time for a chloride analysis to be (5) Although we do not have to analyze for performed is dependent upon two chloride for ninety-six hours, the factors: (a) if the plant's coolant analysis can be performed within the )

water is seawater or brackish water initial sam ling time frame stated in and (b) if there is only a single barrier criterion (1 between primary containment systems and the cooling water. Under both of the above coditions the licensee shall provide for a chloride analysis within k

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NUREG-0737 PAGE 3 CRITERIA RESPONSE

! 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the sample being taken.

For all other cases, the licensee shall provide for the analysis to be completed within four days. The l chloride analysis does not have to be done onsite.

(6) The design basis for plant equipment (6) The radiation exposures to an individual for reactor coolant and containment for the sampling and analysis of the atmosphere sampling and analysis must reactor coolant and containment assume that it is possible to obtain and atmosphere samples will be:

analyze a sample without radiation '

exposures to any indiviual exceedir.g RCS PASS

• the criteria of GDC 19 (Appendix A,10 CFR Part 50) (i.e., 5 rem whole body, Whole Body 2.5 rem 75 rem extremities). (Note that the Extremities 3.8 rem design and operational review criterion was changed from the operational CONTAINMENT ATMOSPHERE limits of 10 CFR Part 20 (NUREG-0578) to the GDC 19 criterion (October Whole Body 0.5 rem 30, 1979 letter from H. R. Denton to Extremities 1.6 rem all licensees)).

(7) The analysis of primary coolant (7) The analysis will be performed as samples for boron is required for outlined in 2(c). '

PWRs. (Note that Rev. 2 of Regulatory Guide 1.97 specifies the need for primary coolant boron analysis capab'ility at BWR plants).

(8) If inline monitoring is used for any (8) In line monitoring will only be used for sampling and analytical capability the containment hydrogen analysis con-specified herein, the licensee shall sistent with NRC " guidance" Technical provide backup sampling through grab Specifications provided in Generic samples, and shall demonstrate the Letter 83-37.

! capability of analyzing the samples.

Established planning for analysis at offsite facilities is acceptable.

i Equipment provided for backup sampling shall be capable of providing j at least one sample per day for seven days following onset of the accident, and at least one sample per week until

the accident condition no longer exists.

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Se NUREG-0737 l*

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j CRITERIA RESPONSE

(9) The licensee's radiological and (9) a. Liquid

Since the initial sample will chemical sample analysis capability be a 30:1 dilution, a 0.1 m1 from the shallinclude provisions to: sample syringe can tggnjected to a one liter ___.... .. flask,

a. Identify and quantify the isotopes of obtaining a 10,000:1 dilution.

the nuclide categories discussed Additional similar dilutions can be above the levels corresponding to performed.

the source terms given in Regulatory Guide 1.3 or 1.4 and Containment Atmosphere: The grab 1.7. Where necessary and sample from the containment practicable, the ability to dilute atmosphere can be diluted by injecting I

samples to provide capability for a 0.1 m1 sample into an four liter

. measurement and reduction of marinelli providing a 40,000:1 l personnel exposure should be dilution. If further dilutions are provided. Sensitivity of onsite needed, additional similar dilutions can liquid sample analysis capability be performed.

should be such as to permit measurement of radionuclide b. For low levels of background concentration in the range from interferences, a background approximately lu Ci/g to 10 C1/g. subtract routine can be performed.

If the radiation background levels

b. Restrict background levels of are excessive .he samples can be

...ddiation in the radiological and counted in our mobile laboratory 4 chemical analysis faellity from which has complete gamma j sources such that the sample counting faellities.

analysis will provide results with an

' acceptably L small error (approximately a factor bf 2). This ca'n be accomplished through the use of sufficient shielding around sa:nples and outside sources, and by the use of a ventilation system design which will control the '

presence of airborne radioactivity.

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(10) Accuracy, range and sensitivity shall be (10) Ga'mma Spectrum -

The chemical j adequate to provide pertinent data to laboratory's germanum detectors are

the operator in order to describe calibrated periodically with NBS i

radiological and chemleal status of the traceable radionuclides. These i ractor coolant systems. detectors have participated in the NRC Intercomparison Mobile Laboratory Tests. t i

, Boron, Hydrogen, and Chloride i accuracles will be submitted after in-house testing is completed.

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NUREG-0737 PAGE 5 l

RESPONSE

pH - The pH shall be determined by the CRITERIA determination of the boron and phosphate concentrations which shall I be determined by the Dionex lon chromatograph.

i (11) In the design of the post accident (11) Since the PASS will be utilized, these sampling and analysis capability, considerations have already been

. consideration should be given to the submitted, reviewed and approved by following items: the NRC.

a. Provisions for purging sample lines, for reducing plateout in sample -

lines, for minimizing sample loss or distortion, for preventing blockage of sample lines by loose material in the RCS or containment, for appropriate disposal of the samples, and for flow restrictions to limit reactor coolant loss from a rupture of the sample line. The post

_ accident reactor coolant and containment atmosphere samples should be representative of the reactor coolant in the core area and '

the containment atmosphere following a transient or accident.

The sample lines should be as short as possible tominimize the volume of fluid to be taken from

. containment. The residues of sample collection should be returned to containment or to a closed system. .

b. The ventilation exhaust from the sampling station should be filtered with charcoal absorbers and high-efficiency particulate air (HEPA) filters.

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- - - - ~-~-..n . e m. m

, e' MEETING

SUMMARY

DISTRIBUTION Licensee: Baltimore Gas and Electric Company l

• Copies also sent to those people on service (cc) list for subject plant (s).

NRC PDR L PDR ORB #3 Rdg DJaffe EButcher

-BGrimes OELD

! EJordan, IE ACRS-10 PMorriette NRC Meeting

Participants:

FWitt JWing JWhite VBenaroya

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