ML20134L686

Proposed Tech Spec Changes to Tables 3.7-4 & 3.6.3-1 Re Primary Containment Isolation Valves to Reflect Drywell Pneumatic Sys Mods

ML20134L686
Person / Time
Site:	Hatch
Issue date:	08/23/1985
From:	GEORGIA POWER CO.
To:
Shared Package
ML20134L663	List: ML20134L661 ML20134L686
References
TAC-59558, TAC-59559, TAC-59588, TAC-59589, NUDOCS 8509030378
Download: ML20134L686 (9)

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I ENCLOSURE 1 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 ,

EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 l REQUEST TO REVISE TECHNICAL SPECIFICATIONS DRYWELL PNEUMATIC MODIFICATIONS The proposed changes revise Table 3.7-4 of the Unit 1 Technical Specifications and Table 3.6.3-1 of the Unit 2 Technical Specifications to add or delete primary containment isolation valves. The changes reflect drywell pneumatic system modifications planned for implementation in Unit _1 during the Fall 1985 refueling outage and already completed in Unit 2.

The modification divides the original single drywell pneumatic header into two separate headers which penetrate the drywell at different locations. Each header supplies approximately half of the safety / relief valves. The headers are routed such that no high energy line break could damage both headers, thus assuring a long-term pneumatic supply to some safety / relief valves.

Containment isolation, provided in the original design by valves P70/2P70-F004 and F005 in a parallel arrangement (and check valve 2P70-F020 in Unit 2), is provided in the- modified system by valves P70/2P70-F004 and F005 on one header and P70/2P70-F066 and F067 on the other header. Figure 1 provides a simplified diagram of the original and modified isolation valve configurations.

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ORIGINAL CONFIGURATION O

!U4 i W PNE'UMATIC m I , PNEUMATIC SUPPLY

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F005 m W

NOTE: F020 ON UNIT 2 ONLY FIGURE lb ,-

MODIFIED CONFIGURATION

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F005 N-F004 PNEUMATIC m SUPPLY

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> 4---

PNEUMATIC

> COMPONENTS 4---

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ENCLOSURE 2 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST TO-REVISE TECHNICAL SPECIFICATIONS DRYWELL PNEUMATIC MODIFICATIONS Pursuant to 10 CFR 50.59, the Plant Review Board and Safety Review Board have reviewed the attached proposed amendments to the Plant Hatch Units 1 and 2 Technical Specifications and have determined that implementation of the proposed amendments does not constitute an unreviewed safety question.

1. PROPOSED CHANGE Add valves P70-F066 and F067 to Table 3.7-4 of the Unit 1 Technical Specifications.

BASIS The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR because the system will operate in the same manner as before the change. The possibility of an accident or malfunction of a different type than any analyzed in' the FSAR would not be created because no new mode of failure is introduced. The margin of safety as defined in the Technical Specifications is not reduced because a greater degree of containment isolation capability is provided.

2. PROPOSED CHANGE Add valves 2P70-F066 and F067 to Table 3.6.3-1 of the Unit 2 Technical Specifications. Delete valve 2P70-F020 from Table 3.6.3-1.

BASIS

.The probability of occurrence and the consequences of an accident or malfunction of equipment important to safety are not increased above those analyzed in the FSAR because the system operates in the same manner as before the change. The possibility of an accident or malfunction of a different type than analyzed in the FSAR does not result from this change because no new mode of failure is introduced.

The margin of safety as defined in the Technical Specifications is not

, reduced because the change assures that the same degree of containment isolation capability is maintained.

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ENCLOSURE 3 NRC 00CKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS DRYWELL PNEUMATIC MODIFICATIONS Pursuant to 10 CFR 50.92, Georgia Power Company has evaluated the attached proposed amendment for Plant Hatch Units 1 and 2 and has determined that their adoption would not involve a significant hazard. The basis for this determination is as follows:

1. PROPOSED CHANGE

' Add valves P70-F066 and F067 to Table 3.7-4 of the Unit 1 Technical Specifications.

BASIS This change constitutes an additional control not previously included in the Technical Specifications. This change does not affect the probability or consequences of an accident or malfunction analyzed in the FSAR. This change does not create the possibility of an accident or malfunction of a different type than analyzed in the FSAR. The margin of safety as defined in the basis for any Technical Specification is not affected. The effect of this change is therefore within the acceptance criteria and the change is consistent with Item (ii) of the " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6, 1983 issue of the Federal Register.

2. PROPOSED CHANGE Add valves 2P70-F066 and F067 to Table 3.6.3-1 of the Unit 2 Technical Specifications.

BASIS This change constitutes an additional control not previously included in i Technical Specifications. This change does not affect the probability or consequences of an accident or malfunction analyzed in the FSAR.

This change .does not create the possibility of an accident or malfunction of a different type than analyzed in the FSAR. The margin of safety as defined in the basis for any Technical Specification is not affected. The effect of this change is therefore within the acceptance criteria and the change is consistent with Item (ii) of the " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards Considerations" listed on page 14870 of the April 6, 1983 issue of the Federal Register.

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ENCLOSURE 3 (Continued)

NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST TO REVISE TECHNICAL SPECIFICATIONS DRYWELL PNEUMATIC MODIFICATIONS

3. PROPOSED CHANGE Delete. valve 2P70-F020 from Table 3.6.3-1 of the Unit 2 Technical Specifications.

BASIS This is a purely administrative change to the Technical Specifications.

This change reflects a plant modification which eliminated the need for valve 2P70-F020 for containnent isolations. This change does not affect the probability or consequences of an accident or malfunction analyzed in the FSAR. This change does not create the possibility of an accident or malfunction of a different type than any analyzed in the FSAR. The margin of safety as defined in the basis for any Technical Specification is not affected by the ch'ange. The effect of the change is therefore within the acceptance criteria and the change is consistent with Item (i) of the " Examples of Amendments That Are Considered Not Likely to Involve Significant Hazards considerations" listed on page 14870 of the April 6, 1983 issue of the Federal Register.

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ENCLOSURE 4 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNITS 1, 2 REQUEST T0 REVISE-TECHNICAL SPECIFICATIONS DRYWELL PNEUMATIC MODIFICATIONS The proposed change to the Units 1 and 2 Technical Specifications (Appendix A to Operating Licenses DPR-57 and NPF-5) would be incorporated as follows:

Remove Page Insert Page 3.7-24 (Unit 1) 3.7-24 (Unit 1) 3/4 6-24 (Unit 2) 3/4 6-24 (Unit 2) 3/4 6-28 (Unit 2) 3/4 6-28 (Unit 2)

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Table 3.7-4 (Continued)

Primary Containment Testable Isolation Valves Penetration Number- Valve Designation Notes X P51-F513 & F514 (1) (2) (4) (5) (9)

X-22 P70-F004, F005 (1) (2) (4) (5) (10)

X-25 T48-F307, F308, F309, F103 & F324 (1) (2) (4) (5) (9)

X-25 T48-Fil3 & F114 (1) (2) (4) (5) (9)

X-25 T48-F321 & F322 X-25 T48-F104, F118A, F1188 (1) (2) (4) (5) (9)

X-26 T48-F319 & F320 (1) (2) (4) (5) (9)

X-26 T48-F334A & F335A X-26 T48-F3348 & F3358 "

X-26 T48-F340 & F341 "

X-26 P33-F002 & F010 X-27F P70-F066, F067 (1) (2) (4) (5) (10)

X P33-F003 & F011 (1) (2) (4) (5) (9)

X-31 P33-F004 & F012 "

X-36 C11-F086 (1) (2) (4) (5) (10)

X-36 C11-F083 "

X-39A Ell-F016A & F021A (1) (2) (4) (5) (9)

X-39A Ell-F0168 & F0218 "

X-40 P70-F002 & F003 "

X-41 B21-F019 & F020 X-42 C41-F006 (1) (2) (4) (5) (10)

X-42 C41-F007 X-46 P21-F353 & F406 (1) (2) (4) (5) (9)

X-203 E-51-F003 & F031 X-204A Ell-F065A & F004A (1) (2) (5) (9) (12) 3.7-24

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TABLE 3.6.3-1 Contirued 9

- PRIMARY CONPADNENT ISOLATION VALVES i

-g VALVE FINCTION AND NLNBER 4 B. MANUAL ISOLATION VALVES (e) g

1. Main steam isolation valtes 2E32-F001B, F, K, P

2. MIR return to reciro.11ation loop isolation valtes 2 Ell-F015A, B

3. IOCA H2 recombiner isolation valves 2T49-F002 A, B 2r49-F004 A, B qa

4. Core spray isolation valves 2E21-F005A, B T

g 5. Service air isolation valses 2P51-F651 2P51-F513 i

6. RBCCW alpply ard return isolation valtes 2P42-F051 2P42-F052 (e) Includes power operated valves which do not isolate altomatically.

TABLE 3.6.3-1 (Contin 1ed)

PRIMARY ENTAI!NEtff ISOIATION VALVES VALVE FUNCTION AND NUMBER C. OIHER ISOLATION VALVES N 1. Primary feedwater isolation valtes 2B21-F010 A, B 2B21-F077 A,(f) B(f)

2. Drywell pneumatic ret 11rn isolation valves 2P70-F004 2P70-F005 2P70-F066 2P70-F067

3. Recirculation line flow instmmentation line isolation valtes(9) w 2B31-F009 A, B, C, D 1 2B31-F010 A, B, C, D m 2B31-F011 A, B, C, D h

co 2B31-F012 A, B, C, D

4. Recira11ation punp seal purge isolation valtes 2B31-F013 A, B 2B31-F017 A, B

5. Recirallation line presaire instmmentation line isolation valves (9) 2B31-F057 A, B

6. Recira11ation panp discisma presaire instmmentation line isolation valtes(9) 2B31-F040 A, D (f) Air assist check valte (9) Excess flow check valte