ML20079F424
| ML20079F424 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 04/27/1982 |
| From: | Benaroya V Office of Nuclear Reactor Regulation |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20079F427 | List:
|
| References | |
| FOIA-84-35, TASK-2.B.3, TASK-TM NUDOCS 8205120076 | |
| Download: ML20079F424 (4) | |
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g NUCLEAR REGULATORY COMMISSION
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'g,*****,y APR 2 71982 Docket Nos. 50-400/401 MEMORANDUM FOR:
Frank Miraglia, Chief Licensing Branch #3 Division of Licensing l
FROM:
Victor Benaroya, Chief Chemical Engineering Branch
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SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON SPEARON HARRIS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2
' P'iant - flame : -Shearon Harris Nuclear Power Plant, Unit Nos.1 and 2 t
. 5uppliers: Westingho.use Electric Corporation; Carolina Power & Light Company Licensing Stage:
OL i-
. Docket Numbers: 50-400/401 Responsible Branch & Project Manager:
Licensing Branch #3; (unassigned) t Reviewer:
J. Wing Description of Task:
Operating License Review Status:- Request for Additional-Information i-The Chemical Engineering Branch has reviewed Sections TMI 2.1.8.a (Item II.B.3 of TMI Action Plan), 6.1.1, 6.1.2, 6.5.2, 9.1.3, 9.3.2, and 9.3.4 of the Shearon Harris' FSAR.
We need the enclosed additional information on the organic materials (Section 6.1.2) and Spent Fuel Pool Cleanup System (Section 9.1.3) to complete our review.
~In. addition, the applicant has not provided sufficient information on post-
- accident sa.?pling capability (Item II.B.3 in NUREG-0737). We need information that demonstrates.that the applicant meets the provisions stated in the i
anclosed proposed license condition to complete our evaluation on Post-Accident
' Sampling or we will impose the proposed licentse condition.
1 g
Victor Benaroya, Chief Chemical Engineering Branch Division of Engineering
Enclosure:
As-stated cc:
R. Vollmer-S. Pawlicki D. Eisenhut T. Sullivan R. Tedesce J. Wing W. Johnston F. Witt C. McCracken P. Wu
Contact:
J. Wing-g (OPy Hos Been Sent to PDR X27278
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N 281.1 In Section 1.8, Conformance to NRC Regulatory Guides, you stated (1.8,6.1.2) that the Shearon Harris project complies with the requirements of ANSI N101.4-1972, as it is endorsed by Regulstory Guide 1.54 for the containment floor and the containment liner only.
In Section 6.1.2, you indicated that protective coatings applied to equipment, piping, steel surfaces and concrete surfaces have been applied in accordance with ANSI N101.4-1972 and Regulatory Guide 1.54.
Explain the discrepancy between these two statements.
It is our position that both ANSI N101.4-1972 and Regulatory Guide 1,54 are applicable to interior surfaces of the containment as well as exposed surfaces of large equipment inside the containment.
However, small equipment, such as transmitters, alarms, meters, and valves need not be painted in accordance with Regulatory Guide 1.54 and ANSI N101.4-1972.
s 281.2 Indicate the total weight of electrical cable insulation materials t
(6.1.2) that are uncovered and the total weight of cable insulation materials that are in closed metal conduits or closed cable trays inside the containment.'
Provide the chemical composition of these cable insula-tion materials.
Provide a breakdown of cable diameters and associated conductor cross sections, or an equivalent cable diameter and con-ductor cross section that is representative of the total cable surface area associated with the totcl quantity of the cables inside containment.
This information is needed for estimating the hydrogen generation rates as a function of time following a postulated design basis accident.
281.3 Regarding the. Spent Fuel Pool Cleanup System, provide the following (9.1.3) informations Describe the samples and instrumentation and their frequency of measure 3ent that will be performed to monitor the Spent Fuel Pool water purity and need for ion exchanger resin and filter replacement.
State the chamical and radiochemical limits to be used in monitoring
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the spent fuel pool water and for initiating corrective action.
Provide the basis for establishing these limits.
Your response should consider variables such as: gross gamma and iodine activity, demine-ralizer-and/cr filter differential pressure, demineralizer decontamination factor, pH and crud level.
281.4 Provide information that satisfies the attached proposed license (II.B.3; conditions for post-accident sampling.
l TMI 2.1.8.a) i o,
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SAFETY EVALUATION-BY THE OFFICE OF NUCLEAR REACTOR REGULATION SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 CAROLINA POWER & LIGHT COMPANY 4
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DOCKET NOS. 50-400/401 NUREG-0737, II.B.3 - Post Accident Sampling Capability REQUIREMENT Provide a capability to obtain and quantitatively analyze reactor coolant and containment atmosphere samples, without radiation exposure to any indiviaual
. exceeding 5 rem to the whole body or 75 rem to the extremities (GDC-19) during and following an accident in which there is core degrad:, tion.
Materials to be analyzed and quantified include certain radionuclides that are indicators of severity of core damagt. (e.g., noble gases, iodines, cesiums and non volatile
' isotopes), hydrogen in the containment atmosphere and total dissolved gases or Hydrogen, boron and chloride in reactor coolant samples in accordance with the quirements of NUREG-0737.
'To satisfy the requirements, the applicant should (1) review and modify his
. sampling, chemical analysis and radionuclide determination capabilitier as necessary to comply with NUREG-0737, II.B.3, (2) provide the staff with infor-mation pertaining to system design, analytical capabilities and procedures in sufficient detail to demonstrate that the requirements have been met.
EVALUATION AND FINDINGS l The applicant has committed to a n-accident sar.ipling system that meets the l requirements of NUREG-0137. Item II.d.3 in the FSAR, but Las not provided all the technical informatibn required by NUREG-0737 for our evaluation.
Implementa-tion cf the requirement is not necescary prior to low power operation because 4 small quantities'of radionuclide inventory will exist in the reactor coolant 3j systen and therefore will not affect the health and safety of the public.
Prior to exceeding 5% power operation the applicant must demonstrate the capability to
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'promptly obtain reactor coolant samples in the event of an accident in which there f
is core damage _ consistent with the conditions stated below.
1.
Demonstrate compliance with all requirements of NUREG-0737, II.B.3, for sampling, chemical and radionuclide analysis capability, under accident conditions.
2.. Provide sufficient shielding to meet the requirements of GDC-19, assuming Reg. Guide 1.4 source terms.
3.
Commit to meet the sampling and analysis guidelines of Reg. Guide 1.97, Rev. 2.
4.
Verify that all electrically powered ccmponents associated with post accident sampling are capable of being supplied with power and operated, within thirty minutes of an accident in which there is core degradation,
-assuming loss of off site power.
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Verify that valves which are not accessible for repair after an accident are environmentally qualified for the conditions in which they must operate.
6.
Provide a procedure for relating radionuclide gaseous and ionic species to estimated core damage.
7.
State the design or operational provisions to prevent high pressure carrier gas from entering the reactor coolant system from on line gas analysis equipment, if it is used.
8.
Provide a method for verifying that reactor coolant dissolved oxygen is at ( 0.1 ppm if reactor coolant chlorides are determined to be > 0.15 ppm.
9.
Provide information ion (a) testing ~ frequency and type-of testing to ensure long term operability of the post accident sampling system and (b) operator training requirements for post-accident sampling.
In addition to-the above licensing conditions tne staff is conducting a generic review of accuracy and -sensitivity for analytical procedures and on-line instru-mentation to be used for post-accident analysis. We will require that the applicant submit data supporting the applicability cf each selected analytical chemistry pro-cedura or on-line instrument along with documentation demonstrating compliance with the licensing conditions four months prior to exceeding 5% power operation, but review and approval of these procedures will not be a condition for full power operation.
In the event our generic review determines a specific procedure is unacceptable, we will require the applicant to make modifications as determined by our generic review.
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