ML19221B045
| ML19221B045 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-09.3.2, NUREG-75-87, NUREG-75-87-9.3.2, SRP-09.03.02, SRP-9.03.02, NUDOCS 7907120306 | |
| Download: ML19221B045 (4) | |
Text
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STANDARD REVIEW PLAN
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OFFICE OF NUCLEAR REACTOR REGULATION SECTICN 9.3.2 PROCESS SAMPLING SYSTEM Primary - Efflue,t Treatment Systems Branch (ETSB)
Secondary - None I.
MEAS OF RE!IEW ETSB reviews the following information in the applicant's safety analy;is report (SAR):
1.
The design objec.'ves and design criteria for the process sampling syster (PSS) are reviewed at the construction permit (CP) stage. During the operating license (0L) stage of retiew, ETSB review consists of confirming the design accepted at the CP stage and e ating the adequacy of the applicant'$ technical specifications in these areas. The re. view includes identification of the process stre3ms to be sampled and the parameters to be determir.ed through sampling (e.g., gross beta-gamma concentration, boric acid concentration).
2.
The system description for the PSS is reviewed at the cperating license (OL) stage. The review includes (a) piping and instrumentation diagrams (P& ids),
9 (b) provisions for obtaining representative samples, (c) location of supling points and sample stations, and (d) provisions for purging sampling lines.
3.
The seismic design and quality groun classifications of piping and equipment, and the bases for the classifications chosen are reviewed at the CP stage. At the OL stage, the review includes design and expected temperatures and pressures and materials of construction of ccmponents of t b system.
4.
The isolation provisions for the system and the means provided to limit radioactive releases by limitiig reactor coolant losses are reviewed at the CP stage.
Sampling and monitoring systems for radwaste processing systems are reviewed by EISB under SRP Section 11.5.
Secondary reviews are performed by the following branches:
l CSB, under SRP Section 6.2.4, reviews the design of isolation provisions of those l
portionsofthePSSthatpenetrateprimarycontainment;andASB,underSRP3.6.1, reviews l the design with respect to the effects of externally or internally generated missiles, pipe whip, and jet impingement forces associated with postulated pipe breaks in high energy fluid systems or leakage cracks in moderate energy fluid systems.
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Rev. I 148 274
II.
ACCEPTANCE CRITERIA 1.
The applicant's design should be such that the PSS has the capability for samplica all normal process systems and f.rincipal components, incluiing provisions for obtaining samples from at least the following points:
a.
For a pressurized water reactor (PhR):
l Leactor coolant.
Fefueling (borated) water storage tank.
CCC5 core flooding tank.
Concentrated boric acid storage tank.
Boric acid mix tank.
Borun injection tank.
Chemical additive tank.
Spent fuel pool.
Secondary coolant.
Pressurizer tank.
Steam generator blowdown (if applicable).
Secondarycoolantcondensatetreatmentwastej Sumps inside containment.
l Containment atmosphere.
l Offgas storage tanks.
l b.
For a boiling water reactor (B 4R):
Main condenser evacuation system offg35.
Standby liquid control system tank.
Sumps inside containment.
l Spent fuel pool.
l Drywell atmosphere (Mark I & II).
I Cryogenic still inlet line.
I Other sample points that may be included in the P55 but do not require remote sampling are given in SRP Section 11.5.
The required analysis and frequencies should be given in the plant technical l
specifications.
2.
ETSB will use the following guidelines for determining the acceptability of the 3ystem functional design:
a.
Provisions should be made to assure representative samples from liquid process streams and tanks. For tanks, provisions should be made to sample the bulk volume of the tank and to avoid sampling from low points or from potential sediment. traos. For process stream samples, sample points should Rev. 1 9.3.2-2
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be located in turbulent flow zones. Previsions for sampling should be in accordance with the guidelinee in Regulatory Guide 1.24, paition C.6.
l b.
Pravisions should be made to assure representative samples from gaseous process streams and tanks in accordance w'ih ANSI N13.1-1969.
Locations of san.pling points should be described in the SAR at 'he OL stage c.
and should be shown on P& ids describing the system to be sampled.
d.
Provisions shculd be made for purging sampling lines and for reducing plateout in sample lines (e.g., heat tracing).
Provisions should be made to purge and drain sample streams back to the e.
system or origin or to an appropriate waste treatment system.
f.
Isolation valves should fail in the closed position.
g.
Passive flow restrictions to limit reactor coolant loss from a rupture of the sample line should be pruvided.
3.
The seismic design and quality group classification of sampling lines and components should conform to the classification of the system to which each sampling line and component is connected (e.g., a sampling line connected to a Quality Group A and seismic Category I system should be designed to Quality Group A and seismic Category I classifcation) as described in Regulatory Guides 1.26, 1.29 and 1.143.
Components and piping downstream of the second isolation valve can be designed to Quality Group D and nonseismic Category I requirements.
III. REVIEW PROCEDURES The reviewer will select and emphasize material from this review plan, as may be appro-priate for a particular case.
l.
In the review of the process sampling system, ETSB compares the list of process sampling points contained in the SAR with the sampling points identified in subsection II.1, above, to assura that the required process sampling points
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have been provided.
2.
ETSB compares the capability of the system to obtain representative samples of process fluids and the locations of scmpling points with the guidelines for obtaining representative samples of fluids contained in position C.6 of Regulatory Guide 1.21 and with the principles for obtaining representative samples of gases contained ir ANSI N13.1-1969.
148Property "ANSI code" (as page type) with input value "ANSI N13.1-1969.</br></br>148" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process. 276 9.3.2-3 Rev. 1
3.
ETSB compares the seismic design and quality group classifications of the PSS to the classifications of the fluid systems to which the sampling system is connected.
O 4.
ETSB reviews the technical specifications for process sampling to determine that the content and intent of the technical specifications are in agreement with the requirements developed as a result of the staff's review.
5.
ETSB verifies that provisions have been made to limit the potential for reactor coolant loss from the cupture of a sample line and provides AAB with estimates of RCS fluid losses that would result from sample line rupture.
IV.
EVALUATION FINDINGS ETSB verifies that sufficient information has been provided and that the review supports conclusions of the following tyor, to be included in the staff's safety evaluation report:
"The process sampling system includes piping, valves, heat exchangers, and other components associated with the system from the point of sample withdrawal from a fluid system up to the analyzing station, sampling station, or local simpling point. Our review included the provisions proposed to sample all principal fluid process streams associated with p1 ant operation and the applicant's proposed design of these systems. The review has included descriptive information for j
the process sampling system and the lccation of sampling points, as shown on piping and instrumentation diagrams.
"The basis for acceptance in our review has been conformance of the applicant's design for the process sampling system to applicable regulations, guides, and industry standards. Based on our evaluation, we find the prcoosed system to be acceptable."
V.
REFERENCES 1
Regulatory Guide 1.21, " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive M3terials in Liquid and Gaseous Effluents from Iight-Water-Cooled Nuclear Power Plants."
l 2.
Rejulatory Guide 1.26, " Quality Group Classifications and Standards for Water,
5 team, and Radioactive-Waste-Containing Components of Nuclear Power Plants."
l 3.
Regulatory Guide 1.29, " Seismic Design Classification."
l 4
ANSI N13.1-19G9, " Guide to Sampling Airborne Radioactive Materials in Nuclear Facilities," American National Standard 3 Institute (1969).
5.
Regulatory Guide 1.143, " Design Guidance for Radioactive Waste Management Systems, Structures and Ccmponents Installed in Light-Water-Ccoied Nuclear Reactor Power Plants."
9.3.2-4 Rev. 1
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