ML20147B708
| ML20147B708 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/11/1988 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20147B710 | List: |
| References | |
| NUDOCS 8803020167 | |
| Download: ML20147B708 (9) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY DOCKET NO. 50-336 HILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 124 License No. DPR-65 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Northeast Nuclear Energy Company, et al. (the licensee), dated December 28, 1987, as supplemented by letter dated January 5, 1988, 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 l
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 (i) 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 with 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.
SBR " d u Bi8" g6 P
e ATTACHMENT TO LICENSE AMENDMENT NO.124 FACILITY OPERATING LICENSE NO. OPR-65 DOCKET NO. 50-336 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 areas of change.
The corresponding overleaf pages are provided to maintain document completeness.
Remove Insert 3/4 6-2 3/4 6-2 3/4 6-4 3/4 6-4 1
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3/4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 PRIMARY CONTAINMENT 3/4.6.1.1 CONTAINMENT INTEGRITY Primary CONTAINMENT INTEGRITY ensures that the release of radioactive materials from the containment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restriction, in conjunc-tion with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR 100 during accident conditions.
3/4.6.1.2 CONTAINMENT LEAKAGE The limitations on containment leakage rates ensure that the total containment leakage volume will not exceed the value assumed in the accident analyses at the peak accident pressure of 54 psig, P.
As an added conservatism, the measured overall integrated"leakage rate is further limited to 1 0.75 L during performance of the periodic tests to account for possi81e degra-dation of the containment leakage barriers between leakage tests.
The surveillance testing for measuring leakage rates are consistent with the requirements of Appendix "J" of 10 CFR 50, with the option of the use of the mass point method for perforn-ing leakage calculations.
3/4.6.1.3 CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and leak rate given in Specifications 3.6.1.1 and 3.6.1.2.
The limitations on the air locks allow entry and exit into and out of the containment during operation and ensure through the surveillance testing that air lock leakage will not become excessive through continuous usage.
MILLSTONE - UNIT 2 B 3/4 6-1
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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
An overall integrated leakage rate of 5 L, 0.50 a.
percentbyweightofthecontainmentairher24 hours at P,,
54 psig, b.
A combined leakage rate of $ 0.60 L for all penetra-tions and valves subject to Type B $nd C tests when pressurized to P.
3 c.
A combined leakage rate of $ 0.017 L for all penetra-tions identified in Table 3.6-1 as sScondary contain-ment bypass leakage paths when pressurized to P,.
APPLICABILITY: MODES 1, 2,
3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate for all penetrations an(b) with the measured combined leakage rate exceeding 0.75 L, or d valves subject to Types B or (c) with the combined bypass and C tests exceeding 0.60 L,L,
leakage rate exceeding 0.017 restore the leakage rate (s) to 1
within the limit (s) prior to i$ creasing the Reactor Coolant g
System temperature above 200 F.
SURVEILLANCE REQUIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in confor-mance with the criteria specified in Appendix J of 10 CFR 50.
Three Type A tests (Overall Integrated Containment a.
Leakage Rate) shall be conducted at 40 i 10 month intervals during shutdown at P (54 psig) during each 10-year service period.
The t$ird test of each set shall be conducted during the shutdown for the 10-year plant inservice inspection.
MILLSTONE - UNIT 2 3/4 6-2 Amendment No.124 j
CONTAINMENT SYSTEMS SURVEILIANCE REOUIREMENTS (Continued) g.
All test leakage rates shall be calculated using observed data converted to absolute values.
Error arialyses shall be performed to select an acceptable
' integrated leakage measurement system.
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MILLSTONE - UNIT 2 3/4 6-4 A endment No.
124
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UNITED STATES
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g NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20666 O
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMEN 0 MENT NO.124 TO DPR-65 NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
MI,L,L,ST0_NE_ NUCLEAR POWER STATION, UN,IT~ NO. 2 DOCKET NO. 50-336 INTRODUCTION By application for license amendrent dated December 28, 1987, as supplemented by letter dated January 5, 1988, Northeast Nuclear Energy Company (the licensee) requested changes to Millstone Unit 2 Technical Specification (TS) 4.6.1.2, "Containment Leakage" as follows:
(1) the reference to ANSI Standard N45.4-1972 would be deleted and (2) the error analysis requirements would be modified to allow the use of alternate methods. The above changes to the TS have been proposed by the licensee to allow for use of ANSI /ANS Standard 56.8-1981 for "aass point" determination of containment leakage rite and for addressing the inherent errors associated with such testing.
DISCUSSION AND EVALUATION 1he licensee has requested that the reference to ANSI N45.4-1972 in TS 4,6.1.2 be deleted in order to utilize the "mass point" method for integratet. contain-nent leak rate testing. Since the use of the ANSI N45.4-1972 methodology is also required by 10 CFR 50, Appendix J.Section III.A.3, an "exemption from rule" is also required for use of the "mass point" methodology.
It has been recognized by the professi)nal connunity that the rass point rethod is an acceptable means for calculation of containrent leakage in addition to the two other methods, point-to-point and total fre, which are referenced in ANSI N45.4-1972 and endorsed by the present regulatioris. The mass point rethod calculates the air rass at each point in time, and plots it against tine. A linear regression line is plotted through the mass-time points using a least square fit. The slope of this line is proportional to the leakage rate. The mass point tiethod has sone advantages when it is compared with the other nethods.
In the total time method, a series of leakage rates is calculated on the basis of air mass differences between an initial data point and each individual data point thereafter.
If for any reason (such as instru-ment error, lack of teoperature equilibrium, ingassing, or outgassing) the iriitial data point is not accurate, the results of the test will be affected.
In the point-to-point rethod, the leak rates are based on the mass differer.ce between each pair of consecutive points which are then averaged to yield a single leakage rate estimate. Fathematically, this can be shown to be the differer.ce between the air mass at the beginning of the test anc the air trass at the end of the test expressed as a percentage of the containmer,t air r. ass.
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- It follows from the above that the point-to-point method does not make use of any mass readings taken during the test and thus the leakage rate is calculated on the basis of the difference in mass between two measurements taken at the i;e3 J.ning and at the end of the test, which are 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> apart.
ANSI /ANS 56.8-1981, which was intended to replace ANSI N45.4-1972, specifies the use of the rass point method, to the exclusion of the two older rethods.
However, the staff has determined that these three methods (mass point, total time and point-to-point) are acceptable methods which may be used to calculate containment leakage rates. The NRC staff anticipates publishing, for cornrent, a proposed revision to Appendix J that would permit the use of the mass point tr et bed.
In addition to the method of calculation, consideration of the length of the test should also be included in the overall program.
In accordance with Section 7.6 of ANSI N45.4-1972, a test duration less than ?4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is only allowed if approved by the NRC, and the only currently approved methodology for such a test is contained in Bechtel Topical Report RN-TOP-1, Revision 1, "Testing Criteria for Integrated Leakage Rage Testing of Primary Containment Structures for Nuclear Power Plants," dated November 1,1972. This approach only allows use of the total time method. Therefore, the staff will require a minimum test duration of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the mass point method is used. This requirenent is addressed in the associated "exemption a rule. "
Eased upcn the above, we conclude that the use of the "mass point" rrethodology, during a 24-hour containtrent leak rate test is acceptable as is the proposed change to TS 4.6.1.2.
The licensee has also proposed a change to TS 4.6.1.2.g to delete certain wording that requires consider; tion of ".... maximum rreasurement accuracy ar.d instrurrent repeatability" and that, "the measured leakage rates shall be adjusted to include the measurement error." The licensee has proposed alternate wording for TS 4.6.1.2.g as follows:
"Error analyses shall be perfonted to select an acceptable integrated leakage reasurement system."
The proposed TS 4.6.1.2.g confonns, substantially, to the guidance provided by the NRC Staff in the C6 buttion Engineering Standard Technical Spcecificatiers (NUREG-0212. Rev. 2. ;all 1980). Accordingly, the proposed change to the TS is acceptable.
ENVIROWENTAL CONS I D,ER,A,T,1,0,N The NRC staff has considered the environmental impact of the proposed changes to the TS. An "Environnental Assessrrent and Finding of No Significant Irtpact" was published in the Federal Register on February 9, 1988 (53 FR 3801).
i
e 3-CONCLUSION We have concluced, based on the considerations discussed above. that (1) there is reasonable at :e4oce that the health and safety of the public will not be endangered by useration in the proposed manner, and (2) such activities will bc :onducted in compliance with the Commission's regulations, and the issuance of the amenoment will not be inimical to the common defense and securilj or to the health and safety of the public.
i Dated:
February 11, 1988 principal Contributor:
D. Jaffe l
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7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION NORTNEAST NUCLEAR ENEDGY COMPANY d T J.,
_ DOCKET NO. 50-336 NOTICE OF ISSUANCE OF AMENDMENT T_0
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FACILITY U ULATING LICENSE The U.S. Nuclear Regulatory Connission (the Comission) has issued Amendment No.124 to Facility Operating License No. DPR-65, to Northeast Nuclear Energy Company, The Connecticut Light and Power Company, and Western Massachusetts Electric Company, which revised the Technical Specifications for operation of the Millstone Nuclear Power Station, Unit No. 2 located in the
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Town of Waterford, Connecticut. The amendment was effective as of the date of its issuance.
The amendrent provides changes to the Technical Specification (TS) 4.6.1.2, "Containment Leakage" as follows:
(1) the reference to ANSI Standard N45.4-1972 is deleted and (2) the error analysis requirements are modified to allow the use of alternate rethods. In conjuction with an exemption to the requirements of 10 CFR Part 50, Appendix J Section III.A.3, the above changes to the TS allow for use of ANSI /ANS Standard 56.8-1981 for "nass point" determination of
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i certainnent leakage rate and for addressing the inherent errors associated with such testing.
The application for the amendrent complies with the standards and requirenents of the Atomic Energy Act of 1954, as amended (the Act), and the Comissicn ' t rules and regulations. The Comission has made appropriate findings as required by the Act and the Comission's roles and regulations in 10 CFR Chapter I, which are set forth in the license amendnent.
8803020177 880211 PDR ADOCK 05000336 P
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-2 Notice of Consideration of Issuance of Amendment and Opportunity fer Prior Hearing in connection with this action was published in the FEDERAL PEGISTER on January 12, 1988 (53 FR 766).
No request for a hearing or petition (cr leave to intervene was filed following this notice.
The Comission has prepared an Environmental Assessment and Finding of No Significant Impact related to the action and has concluded that an environmental impact statement is not warranted because there will be no envircnmental impact attributed to the action beyond that which has been predicted and described in the Commission's Final Environmental Staternent for the facility dated June 1973.
For further details with respect to this action, see (1) the application for atendment dated December ?8,1987, as supplemented by letter dated January 5,1988,(2) Amendrent No.124 to Facility Operating License No. DRP-65, and (3) the Environrental Assessment and Finding of No Significant Impact (53FR3801). All of these items are available for public inspection at the Comission's Public Document Room,1717 H Street, N.W., Washington, D.C., and at the Waterford Public Library, 49 Rope Ferry Road, Waterford, Connecticut. A copy of items (2) and (3) may be obtained upon recs,est addressed to the U.S.
Nuclear Pegulatory Comission, Washington, D. C. 70555, Attention: Director, Divister. of Reactor Projects I/II.
Cated at Rockville, Maryland, this lith day of February,1988.
FOR THE NUCLEAR REGULATORY COMMISSION
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. -. ~ w David H. h fd, Projec Fanager Project Directorate I d Division of Reactor Projects 1/II