ML19350A054

Forwards Draft Tech Specs 3.4.7.2,4.4.7.2.2 & Table 3.4-1 Re Operational Leakage for RCS & List of RCS Pressure Isolation Valves,In Response to NRC 801006 Request

ML19350A054
Person / Time
Site:	McGuire, Mcguire
Issue date:	11/24/1980
From:	Parker W DUKE POWER CO.
To:	Harold Denton, Youngblood B Office of Nuclear Reactor Regulation
Shared Package
ML19350A056	List: ML19350A054 ML19350A058
References
NUDOCS 8012010201
Download: ML19350A054 (4)

Text

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, a.'s"Ct.a Ci Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Co= mission Washington, D. C. 20555 Attention: Mr. B. J. Youngblood, Chief Licensing Projects Branch No. 1 Re: McGuire Nuclear Station Docket Nos. 50-369, -370

Subject:

Inservice Inspection of Reactor Coolant System Pressure Isolation Valves

Dear Sir:

As requested by Mr. Robert L. Tedesco's letter of October 6, 1980 please find attached a list of .he Reactor Coolant System pressure isolation valves for McGuire Nuclear Station Unit 1. Four sets of piping and instrumentation dia-grams showing the Reactor Coolant System isolation valves have also been attached.

In regard to the conformance of our inservice inspection program with the Staff position as transmitted by Mr. Tedesco's letter, please find attached a draft of the Technical Specification for McGuire Unit 1 on the operational leakage for the Reactor Coolant System. This draft Technical Specification addresses limiting conditions for operation when leakage limits from Reactor Coolant 9 System pressure isolation valves are r.ot met. In addition, surveillance requirements specifying periodic leak testing of each pressure isolation valve are included. The draft Technical Specifications conform to the Staff's posi-tien as follows.

1. Specification 4.4.7.2.2a requires that Reactor Coolant System pressure isolation valves specified in the Technical Specifica-tion be leak tested at least once per 18 months, prior to entering MODE 2 whenever the plant has been in cold shutdown for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been per-formed in the previous nine months, prior to returning the q(\

valve to service following maintenance, repair or replacement U g 8, 8012010/0/ d

Mr. Harold R. Denton, Director November 24, 1980 Page Two work on the valve, and within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action or flow through the valve. Thus, the leak-tight integrity of these valves is insured by periodic leak testing.

2. The Reactor Coolant System pressure isolation valves are not defined as Category A valves, however, these valves will be tested to meet the intent of IWV-3420 of Section XI of ASME Code.

3. As stated above, the draft Technical Specification addresses the limiting conditions for operation in the event that the leakage limits for the Reactor Coolant Svstem pressure isolation valves are not met. The draft Technical Specifica-tion also addresses the surveillance requirements which state the acceptable leak rate testing frequency.

4. The draft Technical Specification, Specification 3.4.7.2.f, limits the leakage for operation to one gpm leakage from any Reactor Coolant System pressure isolation valve listed in the specification.

5. The isolation point which is protected by redundant isolaticn valves is not the Class 1 to Class 2 boundary in the case of the reactor coolant hot leg safety injection. In this instance note that valves NI121A and NI152B are in Class B piping. This piping is designed to withstand design pressure and temperature conditions. Note that these two valves will be reversed pressure tested.

6. The list of Reactor Coolant System pressure isolation valves which have been attached contains the redundant isolation valves in each line. The McGuire Inservice Testing Program for Pumps and Valves requires that each valve be independeatly leak tested.

7. Valves INDlB and IND2A are not required to be tested per Technical Specification 4.4.7.2.2.d which requires testing after valve movement since positive indication of the valve position is shown in the control room.

We would also like to advise you that three additional injection paths were evaluated to determine if the valves in these paths should be categorized as Reactor Coolant System pressure isolation valves. These injection pathways included the normal charging lines, the lines rom the boron injection tank nnd certain valves in the accumulator discharge lines. The normal charging lines and the lines from the boron itijection tank are designed to withstand full

Mr. Harold R. Denton, Director November 24, 1980 Page Three Reactor Coolant System preJsure, therefore, it was determined that the isola-tion valves in these lines dq not form an interface between the high pressure Reactor Coolant System and a low pressure system. Therefore, these valves were not included as Reactor Coolant System pressure isolation valves. Valves in the accumulator discharge lines whose failure could not result in an inter-system LOCA outride containment were also eliminated from the list of Reactor Coolant System p. essure isolation valves.

Please advise if you g have additional questions.

V y truly yours,

' Ow. __, $. 6'A '

William O. Parker,-Jr.

LJB:scs Attachments s

1 J

• 4 4

Table 3.4.1 4

Drawing'No./

Valve Number. Function MC-1562-2.0 INI60 Accumulator Discharge 1NI7] Accumulator Discharge MC-1362-2.1 INI82. Accumulator Discharge.

IN194 Accumulator Discharge MC-1562-3.0

'1 nil 21A* - Safety Injection (Hot Leg) lNI1523* Safety Injection (Hot Leg)

INIl60 Safety Injection (Hot Leg)

INIl57 Safety Injection (Hot Leg)

INI134 Safety Injection (Hot Leg)

INIl26 Safety Injection (Hot Leg)

MC-1562-3.1 INI165 Safety Injection / Residual Heat Removal (Cold Leg)

INIl6;r Safety Injection / Residual Heat Removal (Cold Leg)

. Safety Injection / Residual Heat Removal (Cold Leg)

~

INI169 INIl71- Safety Injection / Residual Heat Removal (Cold Leg)

INIl75 Safety Injection / Residual Heat Removal (Cold Leg)

INIl76 Safety Injection / Residual Heat Removal-(Cold Leg)

INIl80 Safety Injection / Residual Heat Removal (Cold Leg)

INI181 ' Safety Injection / Residual Heat Removal (Cold Leg)

MC-1562-4.0 INI250- Upper Head Injection-

'1NI251 Upper Head Injection INI252 Upper Head Injection 1NI253 Upper Head Injection 1NI249 Upper Head Injection 1NI248 . Upper Head Injection MC-1561-1.0 INDlB** Residual Heat Removal IND2A** Residual Heat Removal

• Reverse Pressure Tested

• • Testing per Section 4.4.7.2.2.d not applicable due to positive indication of valve position in Control Room.