AECM-87-0111, Application for Amend to License NPF-29,redefining Core Alteration to Exclude Normal Movement of Source & Intermediate Range Monitors,Lprms,Traversing in-core Probes & Special Movable Detectors.Fee Paid
| ML20214U386 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/03/1987 |
| From: | Kingsley O SYSTEM ENERGY RESOURCES, INC. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20214U390 | List: |
| References | |
| AECM-87-0111, AECM-87-111, TAC-65511, NUDOCS 8706110170 | |
| Download: ML20214U386 (6) | |
Text
r-EVETEMENERGY REEDEJRCEE, INC.
OMRD K1 GREY.JR E$YcTsawis June 3, 1987 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Document Control Desk Gentlemen:
SUBJECT:
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Proposed Amendment to the Operating License (PC0L-87/04)
RF01 Lessons Learned Technical Specification Changes AECM-87/0)l1 System Energy Resources, Inc. (SERI) is requesting by this submittal an amendment to License NPF-29 for Grand Gulf Nuclear Station Unit 1. This amendment requests two changes to the Grand Gulf Technical Specifications.
The definition of core alteration is changed to exclude normal movement of source range monitors (SRMs) intermediate range monitors (IRMs), local power range monitors (LPRMs), traversing in-core probes (TIPS) or special movable detectors. The second change will reduce the additional snubber sample size after a test failure from 10% to 5% for sample plan 1 of Surveillance Requirement 4.7.4.e.
In accordance with the provisions of 10 CFR 50.30 and 50.4, the signed original of the requested amendment is enclosed and the appropriate copies will be distributed. The attachment provides the complete technical justification and discussion to support the requested amendment. This amendment has been reviewed and accepted by the Plant Safety Review Comittee (PSRC) and the Safety Review Committee (SRC).
Based on the guidelines presented in 10 CFR 50.92, it is the opinion of System Energy Resources, Inc. that this proposed amendment involves no significant hazards considerations.
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r AECM-87/0111 Page 2 In accordance with the requirements of 10 CFR 170.21, we have determined that the application fee is $150. A remittance of $150 is attached to this letter.
Yours uly, I
ODK:bms m (
- Attachments: GGNS PCOL-87/04 -
cc: Mr. T. H. Cloninger.(w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. R. C. Butcher (w/a)
Dr. J. Nelson Grace, Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 Dr. Alton B. Cobb (w/a)
State Health Officer State Board of Health Box 1700 Jackson, Mississippi 39205 h
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m l
BEFORE THE l l
I UNITED STATES NUCLEAR REGULATORY COMMISSION LICENSE NO. NPF-29 DOCKET N0. 50-416 IN THE MATTER OF MISSISSIPPI POWER & LIGHT COMPANY and SYSTEM ENERGY RESOURCES, INC.
and SOUTH MISSISSIPPI ELECTRIC POWER ASSOCIATION AFFIRMATION I, 0. D. Kingsley, Jr., being duly sworn, stated that I am Vice President, Nuclear Operations of System Energy Resources, Inc.; that on- behalf of System Energy. Resources, Inc., and South Mississippi Electric Power Association I am authorized by System Energy Resources, Inc. to sign and file with the Nuclear Regulatory Commission, this application for amendment of the Operating License of the Grand Gulf Nuclear Station; that I signed this application as Vice President, Nuclear Operations of System ergy Resources, Inc.; and that the statements made and the matters set f /therein are true and correct to the best of my knowledge, information an '
fief.
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- 0. DY Kings e .
STATE OF MISSISSIPPI COUNTY OF HINDS SUBSCRIBED AND SWORN T0 before me, a No r Public, in and for the County and State above named, thi ( day of -
f., , 1987.
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Notary Public f
My commission expires:
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A. SUBJECT.
- 1. NLS-87/04 Core Alteration Definition
- 2. Affected Technical Specifications:
- a. Core Alteration Definition, 1.7 - page 1-2
- b. Reactivity Control Systems Shutdown Margin, 3.1.1 - page 3/4 1-1
- c. Reactivity Control Systems Control Rod Maximum Scram Insertion Times, 4.1.3.2 - page 3/4 1-7.
- d. Reactor Protection System Instrumentation, Table 3.3.1 page 3/4 3-4.
- e. Refueling Operations Instrumentation, 3.9.2 - page 3/4 9-3.
- f. Refueling Operations Communications, 3.9.5 - page 3/4 9-7.
B. DISCUSSION The following changes are proposed:
- 1. The definition of Core Alteration is modified to exclude normal movement of the source range monitors (SRMs), intermediate range monitors (IRMs), local power range monitors (LPRMs), traversing in-core probes (TIPS) or special movable detectors.
- 2. The "*" footnote to specification 3.1.1 on shutdown margin is deleted.
This footnote provides an exception to the core alteration definition for movement of IRMs, SRMs or special movable detectors.
- 3. The "*" footnote to Surveillance Requirement 4.1.3.2.a is modified by deleting the exception to the core alteration definition for the movement of SRMs, IRMs or special movable detectors. The exception for normal control rod novement remains and is not affected by this change.
- 4. The "*" footnote to Table 3.3.1-1 is modified by deleting the exceptions to the core alteration definition for IRMs, SRMs or special movable detectors. The part of the "*" footnote requiring operable SRM instrumentation for replacement of LPRM strings is retained.
- 5. The "**" footnote to Specification 3.9.2 on refueling operations instrumentation is deleted. This footnote provides an exception to the core alteration definition for movement of IRMs, SRMs or special movable detectors.
- 6. The "*" footnote to Specification 3.9.5 is modified by deleting the exception to the core alteration definition for incore instrumentation. The part of the "*" footnote that allows an exception for control rod movement with their normal drive system remains and is not affected by this change.
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C. JUSTIFICATION
- 1. The present definition of core alteration includes the addition, removal, relocation or movement of fuel, sources, incore instruments or reactivity controls within the reactor pressure vessel with the vessel head removed and fuel in the vessel. This definition does not specifically address the normal movement of SRMs, IRMs, LPRMs, TIPS or special movable detectors. The purpose of this proposed technical specification change is to provide an exception to the definition of core alteration to address the normal movement of these detectors within the reactor pressure vessel with the vessel head removed and fuel in the vessel. SERI considers normal movement of these detectors to include insertion / withdrawal using detector drives, replacement of the detectors, and movement of special movable detectors in the core region.
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- 2. Present technical specifications allow exceptions to the definition of core alteration for normal movement of IRMs, SRMs, special movable detectors or replacement of LPRM strings. Currently, Table 3.3.1-1 for Reactor Protection System Instrumentation contains a footnote that exempts normal movement of IRMs, SRMs, special movable detectors or replacement of LPRM strings from the restrictions of the core alteration definition. Specification 3.1.1 on Shutdown Margin, Surveillance Requirement 4.1.3.2.a on Control Rod Maximum Scram Insertion times, and Specification 3.9.2 on Refueling Operations Instrumentation currently contain footnotes that exempts normal movement of IRMs, SRMs or special movable detectors from the restrictions of the core alteration definition. Movement of incore instrumentation is currently exempted from the definition of core alteration in Specification 3.9.5 on Refueling Operations Communications. This technical specification change request would clarify the present definition and modify it to include exceptions currently allowed in the technical specifications.
- 3. The TIPS are sealed unit fission detectors and, like the IRMs and SRMs, have their own drive systems for insertion in the reactor core.
For purposes of the core alteration definition, the TIPS should be included in the proposed exceptions and treated similarly as the exceptions provided the IRMs and SRMs in present Specification 3.1.1, 3.9.2, and Surveillance Requirement 4.1.3.2.a.
- 4. During refueling outages, scheduling of work or failures of equipment can place the plant in limiting conditions for operation such that core alterations must be suspended. One example is in Specification 3.8.1.2 for A.C. Sources Shutdown. With all offsite circuits inoperable and/or with diesel generators 11 or 12 inoperable, core alterations are suspended. According to the present definition of core alteration, which includes normal movement of SRMs and IRMs, the weekly functional tests for these detectors could not be performed since their movement in the core is required. The proposed change to the core alteration definition will correct this type of problem.
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- 5. The changes proposed by this submittal have been approved for use at ;
other BWR plants with similar detectors. The changes to the core alteration definition will modify it to include exceptions currently' in the Technical Specifications for SRMs, IRMs, special movable detectors, and LPRM string replacement.
D. SIGNIFICANT HAZARDS CONSIDERATION
- 1. The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. The reactivity worth of the SRMs, IRMs, LPRMs, TIPS and special movable detectors is insignificant and their movement in the core does not have any adverse impact on reactivity excursion events. This change does not involve a change to plant hardware, plant operating procedures or plant emergency procedures. Therefore, this change cannot increase the probability or consequences of an accident.
- 2. The proposed change does not create the possibility of a new or different kind of accident from any previously analyzed. Movement of all detectors in and around the core is controlled by approved procedures. The movement of the small amount of reactivity in the reactor core provided by the subject detectors does not create the possibility of a new accident or different accident from any previously analyzed. ,
- 3. The proposed change does not involve a significant reduction in a margin of safety. The proposed change to the core alteration definition for SRMs, IRMs, LPRMs, and special movable detectors will provide exceptions that are currently allowed in the Technical Specifications. The proposal to exempt the TIPS from the requirements of the core alteration definition is similar to that currently in effect for the other detectors. Therefore, since the proposed changes are similar to present exceptions allowed in the Technical Specifications, no margin of safety is reduced.
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