ML20141K554
| ML20141K554 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 05/22/1997 |
| From: | Kalyanam N NRC (Affiliation Not Assigned) |
| To: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| TAC-M98448, TAC-M98449, NUDOCS 9705290210 | |
| Download: ML20141K554 (5) | |
Text
Mr. J. P. O'Hanlon May 22, 1997 Senior Vice President - Nuclear Virginia Electric and Power Company Innsbrook Technical Center l
5600 Dominion Blvd.
l Glen Allen, Virginia 23060
SUBJECT:
NORTH ANNA UNITS 1 AND 2 - CONTAINMENT GASE0US AND PARTICULATE RADIATION MONITORS (TAC NOS. M98448 AND M98449) i
Dear Mr. O'Hanlon:
l By letter dated March 18, 1997, the Virginia Electric and Power Company l
requested the U.S. Nuclear Regulatory Commission to review the Technical l
Specifications (TS) Bases changes. The proposed TS Bases changes involve l
changes in the seismic qualification for the Containment Gaseous and Particulate Radiation Monitoring System.
Your letter stated that the proposed i
changes do not involve an Unreviewed Safety Question.
Title 10 of the Code of Federal Regulations, Part 50, Section 59 (10 CFR 50.59), permits licensees to make changes in the facility as described in the safety analysis report, without prior Commission approval, unless the proposed change involves a change in the TS incorporated in the license or an unreviewed safety question.
In accordance with your determination stated above, you are authorized to make the proposed TS Bases changes and do not require our review.
The affected TS Bases pages are enclosed.
j It should be noted that all changes to the facility under the 10 CFR 50.59 process and associated safety analysis are subject to future l
inspections / audit, if any.
This completes our effort under the technical assignment control (TAC) numbers M98448 and M98449 and the TACs are closed.
If you have any questions, please write or call me at (301) 415 1480.
Sincerely, (Original Signed By)
N. Kalyanam, Project Manager Project Directorate 11-1 l
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339 DFd 1
1
Enclosure:
As stated cc w/ enc 1:
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Mr. J. P. O'Hanlon North Anna Power Station Virginia Electric & Power Company Units 1 and 2 CC:
Mr. J. Jeffrey Lunsford County Administrator Regional Administrator, Region II Louisa County U.S. Nuclear Regulatory Commission P.O. Box 160 Atlanta Federal Center l
Louisa, Virginia 23093 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303 Michael W. Maupin, Esquire Hunton and Williams Mr. W. R. Matthews,. Manager Riverfront Plaza, East Tower North Anna Power Station 951 E. Byrd Street P. O. Box 402 Richmond, Virginia 23219 Mineral, Virginia 23117 Dr. W. T. Lough Mr. Al Belisle Virginia State Corporation U.S. Nuclear Regulatory Commission Comission Atlanta Federal Center Division of Energy Regulation 61 Forsyth St., SW, Suite 23T85 l
P. O. Box 1197 Atlanta, Georgia 30303 l
Richmond, Virginia 23209 Mr. David Christian, Manager Old Dominion Electric Cooperative Surry Power Station 4201 Dominion Blvd.
Virginia Electric and Power Company l
Glen Allen, Virginia 23060 5570 Hog Island Road.
Surry, Virginia 23883 Mr. M. L. Bowling, Manager Nuclear Licensing & Operations Support Virginia Electric and Power Company i
Innsbrook Technical Center 5000 Dominion i31vd.
Glen Allen, Virginia 23060 l
Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219 Senior Resident Inspector North Anna Power Station U.S. Nuclear Regulatory Commission 1024 Haley Drive Mineral, Virginia 23117 Robert B. Strobe, M.D., M.P.H.
State Health Commissioner Office of the Commissioner i
Virginia Department of Health i
P.O. Box 2448 Richmond, Virginia 23218 l
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l BASES l
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j 3/4,4,6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systerns required by this specification are provided to monitor l
and detect leakage from the Reactor Coolant Pressure Boundary during normal plant operations l
and after seismic events to provide prompt and quantitative information to the operators to permit immediate corrective actions should a Reactor Coolant Pressure Boundary leak be detrimental to the safety of the facihty.
i i
These detection systems are generally consistent with the recommendations of l
Regulatory Guide 1.45," Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973. The containment atmospheric particulate and gaseous radioactivity monitoring system is not fully seismically qualified. Consistent with RG 1.45 these monitors can perform their intended l
function during normal plant operations. To ensure t!'e safety function of detecting reactor coolant pressure boundary leakage is maintained after a seismic event the operability of these monitors is l
required to be verified immediately following a seismic event or the affected units will be shut l
down and cooled down to COLD SHUTDOWN.
l 3/4.4.6.2 OPERATIONAL LEAKAGE 1
l Industry experience has shown that while a limited amount ofleakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value ofless than 1 GPM. This threshold value is sufficiently low.to ensure early detection of additional leakage.
l The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount ofleakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.
l The CONTROLLED LEAKAGE limitation restricts operation when the' total flow ll supplied to the reactor coolant pump seals exceeds 30 GPM with the modulating valve in the 1
l' supply line fully open at a nominal RCS pressure of 2235 psig. This limitation ensures that in the I
event of a LOCA, the safety injection flow will not be less than assumed in the accident analyses.
The total steam generator tube leakage limit of 1 GPM for all steam generators not isolated from the RCS ensures that the dosage contribution frorn the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam l
line break. The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents. In general, for plant operation at or below 50% power, the 500 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.
l NORTH ANNA-UNIT 1 B 3/4 4 4 Amendment No. 409 REVISED BY NRC LETTER DATED 5/22/97 1
REACTOR COOLANT SYSTEM BASES 3/4.4.6 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.6.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the Reactor Coolant Pressure Boundary during normal plant operations and after seismic events to provide prompt and quantitative information to the operators to permit t
immediate corrective actions should a Reactor Coolant Pressure Boundary leak be detrimental to the safety of the facility.
These detection systems are generally consistent with the recommendations of g
Regulatory Guide 1.45 " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973. The containment atmospheric particulate and gaseous radioactivity monitoring system is not fully seismically qualified. Consistent with RG 1 A5 these moniters can perform their intended function during normal plant operations. To ensure the safety function of detecting reactor coolant pressure boundary leakage is maintained after a seismic event the operability of these monitors is required to be verified immediately following a seismic event or the affected units will be shut down and cooled down to COLD SHUTDOWN.
3/4.4.6.2 OPERAT10N AL 1 F AKAGE Industry experience has shown that while a limited amount of leakage is expected from the RCS, the unidentified portion of this leakage can be reduced to a threshold value ofless than i GPM. This threshold value is sufficiently low to ensure early detection of additional leakage.
The 10 GPM IDENTIFIED LEAKAGE limitation provides allowance for a limited amount of leakage from known sources whose presence will not interfere with the detection of UNIDENTIFIED LEAKAGE by the leakage detection systems.
The surveillance requirements for RCS Pressure Isolation Valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent l
intersystem LOCA. Leakage from the RCS Pressure Isolation Valves is IDENTIFIED LEAKAGE
!i and will be considered as a portion of the allowed limit.
i The CONTROLLED LEAKAGE limitation restricts operation when the total flow t
1 supplied to the reactor coolant pump seals exceeds 30 GPM with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig. This limitation ensures that in the event of a LOCA, the safety injection flow will not be less than assumed in the accident analyses.
- The total steam generator tube leakage limit of 1 GPM for all steam generators not isolated from the RCS ensures that the dosage contribution f rom the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steam generator tube rupture or steam line break.
The 1 GPM limit is consistent with the assumptions used in the analysis of these accidents. In i
general, for plant operation at or below 50% power, the 500 gpd leakage limit per steam generator ensures that steam generator tube integrity is mairtained in the event of a men steam line rupture or under LOCA conditions.
NORTH ANNA -IINIT 2 B 3/4 4-4 Amendment No. 96, REVISED BY NRC LETTER DATED 5/22/97 l-
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-w Memorandum Dated:
May'22, 1997 I
Distribution:
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