ML20029B311
| ML20029B311 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/28/1991 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20029B312 | List: |
| References | |
| B13759, GL-89-19, NUDOCS 9103070035 | |
| Download: ML20029B311 (4) | |
Text
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o NORTHEAST UTILITIES om,.i on,c... s.oen si. tw,nn cenceocui I$ 1..^2 I 2 U C 2 P O 00X 770 m m.. e w t. """
HART F ORD. CONNECTICUT 0014i-0270 L
L J C'[C72[.lZ (203) 6 % 4 000 febrrary 28, 1991 Docket No. 50 245 B13759 Re:
10CFR50.90 Generic Letter 89 19 r3AP Topic 1.43 U.S. Nuclear Regulatory Commission Attention: Document Control Desk
-Washington, DC 20555 Gentlemen:
Millstone Nuclear Power Station, Unit No. 1 Pro)osed Revision to Technical Specifications Reactor Hia l Water Letel Feodwater Pump Trio hstrumentation Pursuant to 10CFR50.90, Northeast Nuclear Energy company (NNECO) hereby proposes to amend its Operating License No. DPR 21 by incorporating the changes 'ider,tified in Attachment 1 into the technical specifications of Millstone Unit No. 1.
DJscussion Generic Letter 89-19(I) requested that certain actions be taken for boiling water reactor plants regarding automatic reactor pressure vessel (RPV) over-fill protection, ana that plant procedures and technical specifications should include provisions-to periodically verify the operability of the overfill protection system instrumentation during reactor power operation.
NNEC0 has previously responded to the technical recommendations of Genge Letter 89-19 1990.*3)lstone Unit No.- 1 -in letters dated March 27, for lit 1 1990 and July 26, With regard to the Staff's request for the addition of surveillance (1)
J. G. Partlow letter to All Licensees of Operating Reactors, Applicants for Operating Licenses, and Holders of Construction Permits for Light Water Reactor Nuclear Power Plants, 'Lquest for Action Related to Resolution of Unresolved Safety Issue A 47,
' Safety implication of Control Systems in LWR N. clear-Power Plants' Pursuant to 10CFR50.54(f)--
Gener1c Letter 89 19," cated September 20, 1989.
(2)
E. J. Mroczka letter to U.S. Nuclear Regulatory Commission, " Response to i
Generic letter 8919 -Resolution of Unresolved Safety Issue A 47 " dated
~ March 27, 1990.
(3)
E. J. Mroczka letter to U.S. Nuclear Regulatory Commission, " Supplemental
Response
to Generic Letter 89 19-Resolution of Unresolved Safety issue A-47," dated July 26, 1990.
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1 U.S. Nuclear Regulatory Commission B13769/Page 2 february 28, 1991 requirements, NNECO informed the Staff by letter dated December 24, 1990,I4) that a request to add the RPV overfill protection instrumentation to the Hillstone Unit No. I technical specifications would be submitted by February 28, 1991.
The purpose of this submittal is to provide those changes.
Description of Proposed Chances The proposed changes will add Section 3/4.14.B to the Millstone Unit No, I technical specifications.
This section explicitly requires that the reactor high water level feedwater pump trip instrumentation be operable d'1 ring reactor power operation.
The proposed limiting condition for operation (LCO) and surveillance requirements are consistent with the requirements of existing plant technical specifications for instrument channels that initiate protec-tive actions.
The instrument functional test will be performed on the trip circuit once per operating cycle.
The iristrumentation will be calibrated once per operating cycle with the exception of Level Indicating Transmitter Switches LITS 263 59A and B, which will be calibrated on an annual basis as is cer: aly the case, in addition, an instrument check will be performed once per day.
Currently, Millstone Unit No. I performs these surveillance require-mente per plant procedures.
The proposed license amendment formalizes these requirements into the technical specifications.
Sinnificant Hazards Consideration The proposed additions to the Millstone Unit No. I technical specifications have been reviewed in accordance with the criteria of 10CFR50.92.
NNECO has determined that the changes do not involve a significant hazards considera-tion. Specifically, it has been concluded that the changes do not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated.
The additions to the technical specifications are being proposed in response to Generic Letter 8919.
Specifications for the operation and surveillance of reactor high water level feedwater pump trip instrumenta-tion tre being added.
The additional requirements for operability and survallance of this instrumentation are presently contained in plant procedures, and thus adding the requirements to the technical specifica-l ti'ans will not increase the probability or consequences of any transients or accidents.
L i
(4)
E. J. Mroczka letter to U.S.
Nuclear Regulatory Commission, " Generic letter 89-19," dated December 24, 1990, l
1
j U.S. Nuclear Regulatory Commission B13759/Page 3 February 28, 1991 2.
Create the possibility of a now or different kind of accident from any previously analyzed.
No new failure modes are introduced by the addition of the RPV operation and surveillance specifications to the technical specifications. Modify-ing technical specifications to formally add surveillance requirements already in place with plant procedures and adding a note concerning test frequency will not modify plant response to any operational or transient event.
Neither will this addition create a new nor cause a diffe.et kind of accident from any previously analyzed.
3.
Involve a significant reduction in a margin of safety.
The formal surveillance requirements being added in this change are consistent with what is currently performed for similar instrumentation i
with requirements already in technical specifications, and the added requirements are consistent with what is currently done for this instru-mentation via plant procedures.
Application of the note concerning test frequency is consistent with its application to instruments performing similar safety functions.
Therefore, there is no impact on the margin of safety.
The Commission has provided guidance concerning the application of standaras in 10CFR50.92 by providing certain examples (51FR7751, March 6, 1986) of amendments that are considered not likely to involve a significant hazards consideration.
The changes proposed herein are most closely enveloped by Example (ii), a change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications; e.g.,
a more stringent surveillance requirement.
As discussed previously, Section 3/4.14.B is being added to include require-ments for operability and surveillance for reactor high water level feedwater pump trip instrumentation.
in the current technical specifications there is no specification for the surveillance requirements for RPV overfill instrumen-tation.
The proposed changes formalize existing plant procedure requirements for operability and surveillance of the reactor high water level feedwater j.
pump trip instruments.
L l
Based upon the information contained in this submittal, there are no signifi-cant radiological or nonradiological impacts associated with the proposed changes, and the proposed license amendment will not have a significant effect on the quality of the human environment.
I The Millstone Unit No.1 Nuclear Review Board has reviewed and approved the l
attached proposed revision and has concurred with the above determinations.
l This change is not required to support continued plant operation and can be
{
implemented within 60 days upon issuance.
No specific schedule for issuance I
of this proposed amendment is requested.
o U.S. Nuclear Regulatory Commission B13759/Page 4 February 28, 1991 In accordance with 10CFR50.91(b), we are providing the State of Connecticut with a copy of this proposed amendment application.
Very truly yours, NORTHEAST NVCLEAR ENERGY COMPANY F
E.
J.~ roczka (/
Senior Vice President cc:
- 1. T. Martin, Region 1 Administrator D. H. Jaffe, NRC Project Manager, Millstone Unit Nos. I and 3 W. J. Raymond, Senior Resident inspector, Millstone Unit Nos. 1, 2, and 3 Mr. Kevin McCarthy, Director Radiation Control Unit Department of Environmental Protection Hartfnrd, CT 06106 STATE OF CONNECTICUT)
) ss. Berlin COUNTY OF HARTFORD )
Then personally appeared before me, E. J. Mroczka, who being duly sworn, did state that he is Senior Vice President of Northeast Nuclear Energy Company, a Licensee herein, that he is authorized to execute and file the foregoing information in the name and on behalf of the Licensee herein, and that the statements contained in said information are true and correct to the best of his knowledge and belief.
Me W btLw_
Nota'ry Public l
1
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