ML20116K091
| ML20116K091 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/09/1992 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20116K093 | List: |
| References | |
| DPR-50-A-165 NUDOCS 9211170009 | |
| Download: ML20116K091 (5) | |
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UNITED STATES e
NUCLEAR REGULATORY COMMISSION g
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WASHINGTON. D. C. 20555
,o METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY GPV NVCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 165-License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application 'or amendment by GPU Nuclear Corporation, et al.
(the licensee) dated August 24, 1992, 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 Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i
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 i
been satisfied.
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Accordingly, the license is amended by changes to the Technical Specificatiens as indicated in the attachment to this license amendment, and paragraph 2.c.(2) of Facility Operating License No.
I DPR-50 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 165, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the j
facility in accordance with the Techrical Specifications.
i 3.
This license-amendment is effective ac of its date of-issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
John F. S olz, Director.
Project Directorate I-4 Division of Reactor Projects - I/II l
^'fice of Nuclear Reactor Regulation
Attachment:
l Changes to the l
Technical Specifications f
Date of Issuance:
November 9, 1992 e
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ATTACHMENT TO LICENSE AMENDMENT NO. 165 FACILITY OPERATING LICENSE NO. DPR
- 4 I
i DOCKET NO. 50-289 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by amendm9nt number and j
contain vertical lines indicating the area of change.
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i Remove Insert t
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3-23 3-23 L
3-24 3-24 i
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.I 3.3.3 Exceptions to 3.3.2 shall be as follows:
a.
Both core flood tanks shall be operable at all times.
b.
Both the motor operated valves associated with the core flood tanks shall be folly open at all times.
c.
One reactor building cooling fa:; and associated cooling unit shall be permitted to be out-of-service for seven days.
3.3.4 Prior to initiating maintenance on any of the components, the duplicate (redundant) component shall be verified to be operable, fliutti The requirements of Specificatfon 3.3.1 assure that, before the reactor can be made critical, adequate engineered safety features are operable. Two engineered safeguards makeup pumps, two decay heat removal pumps and two decay heat removal coolers (along with their respective cooling water systems components) are specified.
However, only one of each is necessary to supply emergency coolant to the reactor in the event of a loss-of-coolant accident.
Both core flooding tanks are required because a single core flooding tank has insufficient inventory to reflood the core for hot and cold line breaks (Reference 1).
The operability of the borated water storage tank (BWST) as part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA (Reference 2).
The limits on BWST minimum volume and boron concentration ensure that 1) sufficient water is available within containment to permit recirculation cooling flow to the core, and 2) the reactor will remain at least one percent subcritical at 70'F without any control rods in the core following mixing of the BWST and RCS water volumes (Reference 3).
The contained water volume limit of 350,000 gallons includes an allowance for water not usat'le because of tank discharge location. The limits on 4
contained water volume, Na0H concentration and boron concentration ensure a pH value of between 8.5 and 11.0 of the solution sprayed within containment after a design basis accid P.
The minimum pH of 8.5 assures that iodine will remain in solution whiie the maximum pH of 11.0 minimizes the potential for caustic damage to mechanical systems and components.
Redundant heaters maintain the borated water supply at a temperature greater than 40*F.
3-23 Amendment No. 149, 157, 165
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The post-accident reactor building emergency cooling may be accomplished by three emergency cooling units, by two spray systems, or by a combination of i
one emergency cooling unit and one spray system. The specified requirements j
assure that the required post-accident components are available.
l The iodine removal function of the reactor building spray system requires one spray pump and sodium hydroxide tank contents.
4 The spray system utilities common suction lines with the decay heat removal system.
If a single train of equipment is removed from either system, the other train must be assured to be operable in each system.
2 When the reactor is critical, maintenance is allowed per Specification 3.3.2 j
and 3.3.3 provided requirements in Specification 3.3.4 are met which assure operabilityoftheduplicatecomponents.
The specified maintenance times are a maximum. Operability of tne specified components shall be based on the satisfactory completion of surveillance and inservice testing and inspection required by Technical Specification-4.2 and 4.5.
The allowable maintenance period of up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> may be utilized if the 1
i operability of equipment redundant to that removed from service is verified bated on the results of surveillance and inservice testing and inspection required by Technical Specification 4.2 and 4.5.
j In the event that the need for emergency core cooling should occur, operation of one makeup pump, one decay heat-removal pump, and both core flood tanks will protect the core.
In the event of a reactor coolant system rupture their operation will limit the peak clad temperature to less than t
2,300"F and the metal-water reaction to that representing less than 1 percent of the clad.
Two nuclear service river water pumps and two nuclear service closed cycle cooling pumps are required for normal operation. The normal operating requirements are greater than the emergency requirements following a los s-of-cool ant.
REFERENCES l
(1) VFSAR, Saction 6.1
" Emergency Core Cooling System" (2) VFSAR, Section 14.2.2.3 "Large Break LOCA" (3) UFSAR, Section 14.2.2.1
" Fuel Handling Accident" i
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l 3-24 Amendment No. 80, 149, 157, 165 4